FUS-TN-SA-SE-R-100 ENTE PER LE NUOVE TECNOLOGIE, L'ENERGIA E L'AMBIENTE Associazione ENEA-EURATOM sulla Fusione FUSION DIVISION NUCLEAR FUSION TECHNOLOGIES POST TEST ANALYSIS OF THE EXPERIMENTS P1-P8 IN THE ICE FACILITY USING THE ECART CODE S. Paci (1) M. T. Porfiri(2) EFDA Task TW3-TSS-SEA5.5 Milestone 5 bis (1) Pisa University Via Diotisalvi 2, I-56100, Pisa , Italy e-mail: [email protected] (2) Fusion Unit Via E. Fermi 45, I-00044, Frascati (Rome), Italy e-mail: [email protected] February 2004 Associazione ENEA-EURATOM sulla Fusione Title: DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 2 of 117 Post test analysis of the experiments P1-P8 in the ICE facility using the ECART code Reference: European Fusion Development Agreement Workprogramme 2003 EISS3 Cadarache EFDA task TW3-TSS-SEA5.5 Validation of computer code and model Milestone 5 bis Authors: S. Paci (Pisa University, Pisa, Italy) M. T. Porfiri (ENEA FUS TEC, C.R. Frascati, Italy) Scope: Signatures This work is related to the application of the ECART code (property of CESI and EdF) on the evaluation of the thermalhydraulic transients for eight calculations of the modified Integrated ICE test facility (JAERI). In this report, the ECART results in post test calculations are presented. Results obtained by ECART have shown a quite good capability of the code to simulate the experimental conditions of the ICE facility. Activities relating to code validation has been promoted inside the Euratom Fusion Technology Programme to test the capability of codes in simulating phenomena expected in case of accidents, generally, in fusion facilities and, specifically, in the ITER (International Thermonuclear Experimental Reactor) plant. The activities have been also carried out in the general framework of the validation phase of the ECART code, initially developed for integrated analysis of severe accidents in LWRs, for its application on incidental sequences related to fusion plants. ECART was originally designed and validated for safety analyses of fission NPPs and is internationally recognized as a relevant nuclear source term code for these fission plants. It permits the simulation of chemical reactions and transport of radioactive gases and aerosols under two-phase flow transients in generic flow systems, using a built-in thermal-hydraulic model. Issued by Reviewed by Approved by M. T Porfiri T. Pinna A. Pizzuto Associazione ENEA-EURATOM sulla Fusione Distribution list: DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 M. Samuelli, Fusion Division (ENEA, FUS Frascati, Italy) Technologies (ENEA, FUS TEC Frascati, Italy) A. Pizzuto L. Di Pace T. Pinna L. Topilski (ITER JWS, Garching, Germany) W. Gulden, E. Eriksson (EFDA, Garching, Germany) G. Cambi (Bologna University, Bologna, Italy) X. Masson (Technicatome, Aix en Provence, France) T. Marshall, B. Merril (INEEL, Idaho Falls, U.S.) P. Sardain (CEA, Cadarache, France) K. Takase (JAERI, Naka, Japan) Z. Yitbarek (NFR, Studsvik, Sweden) ENEA FUS-TEC Secretarial Staff Authors: S. Paci (Pisa University, Pisa, Italy) M. T. Porfiri (ENEA, FUS, Frascati, Italy) Archive PAGE 3 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 4 of 117 SUMMARY This work is related to the application of the ECART code (property of CESI and EdF) on the evaluation of the thermal-hydraulic transients for eight calculations of the modified Integrated ICE test facility (JAERI). In this report, the ECART results in post test calculations are presented. Results obtained by ECART have shown a quite good capability of the code to simulate the experimental conditions of the ICE facility. Activities relating to code validation has been promoted inside the Euratom Fusion Technology Programme to test the capability of codes in simulating phenomena expected in case of accidents, generally, in fusion facilities and, specifically, in the ITER (International Thermonuclear Experimental Reactor) plant. The activities have been also carried out in the general framework of the validation phase of the ECART code, initially developed for integrated analysis of severe accidents in LWRs, for its application on incidental sequences related to fusion plants. ECART was originally designed and validated for safety analyses of fission NPPs and is internationally recognized as a relevant nuclear source term code for these fission plants. It permits the simulation of chemical reactions and transport of radioactive gases and aerosols under two-phase flow transients in generic flow systems, using a built-in thermal-hydraulic model. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 5 of 117 INDEX 1. INTRODUCTION....................................................................................................................11 2. MAIN CHARACTERISTICS OF THE ECART CODE .....................................................13 2.1 Main Features of the Code...................................................................................................13 2.1.1 Thermal-Hydraulic Models.........................................................................................15 2.1.1.1 Evaluation of Heat Transfer Coefficients ..........................................................................16 2.1.2 Aerosol and Vapour Models .......................................................................................17 2.1.2.1 2.1.2.2 2.1.2.3 Transport of Volatile Substances..................................................................................17 Transport of Aerosol Particles ......................................................................................18 Coupling Between Aerosol and Thermal-Hydraulic Calculations ..........................21 2.1.3 Chemistry Models ........................................................................................................21 2.1.3.1 3. Models for Chemical Reactions in Fusion Reactor Accidents...........................................22 INTEGRATED ICE TEST FACILITY DESCRIPTION ....................................................27 3.1 ICE Main Components ........................................................................................................28 3.1.1 Boiler ...............................................................................................................................28 3.1.2 Plasma Chamber..............................................................................................................29 3.1.3 Simplified Vacuum Vessel..............................................................................................29 3.1.4 Divertor Orifice Plate ......................................................................................................30 3.1.5 Drain Tank.......................................................................................................................31 3.1.6 Suppression Tank ............................................................................................................32 3.2 Test Protocol .........................................................................................................................32 4. INPUT ASSUMPTIONS .........................................................................................................34 4.1 Control Nodes .......................................................................................................................35 4.2 Junctions................................................................................................................................35 4.3 Heat Transfer Structures.....................................................................................................37 4.4 Boundary Conditions ...........................................................................................................38 5. RESULTS FROM CALCULATIONS OF ICE P1-P8 TESTS............................................40 5.1 ICE CASE P1........................................................................................................................40 5.1.1 Main results .....................................................................................................................40 5.1.2 Analysis of the results .....................................................................................................40 5.2 ICE CASE P2........................................................................................................................43 5.2.1 Main results .....................................................................................................................43 5.2.2 Analysis of the results .....................................................................................................43 5.3 ICE CASE P3........................................................................................................................46 5.3.1 Main results .....................................................................................................................46 5.3.2 Analysis of the results .....................................................................................................46 5.4 ICE CASE P4........................................................................................................................48 5.4.1 Main results .....................................................................................................................48 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 6 of 117 5.4.2 Analysis of the results .....................................................................................................48 5.5 ICE CASE P5........................................................................................................................50 5.5.1 Main results .....................................................................................................................50 5.5.2 Analysis of the results .....................................................................................................50 5.6 ICE CASE P6........................................................................................................................52 5.6.1 Main results .....................................................................................................................52 5.6.2 Analysis of the results .....................................................................................................52 5.7 ICE CASE P7........................................................................................................................55 5.7.1 Main results .....................................................................................................................55 5.7.2 Analysis of the results .....................................................................................................55 5.8 ICE CASE P8........................................................................................................................57 5.8.1 Main results .....................................................................................................................57 5.8.2 Analysis of the results .....................................................................................................57 6. CONCLUSIONS FOR ICE TESTS P1 - P8 CALCULATIONS .........................................59 REFERENCES .................................................................................................................................62 APPENDIX A: ECART INPUT DECK FOR TEST P1...............................................................64 APPENDIX B: OUTPUT COMPARISON TABLES AND PLOTS ...........................................69 B.1 Test P1 ...................................................................................................................................70 B.2 Test P2 ...................................................................................................................................76 B.3 Test P3 ...................................................................................................................................82 B.1 Test P4 ...................................................................................................................................88 B.1 Test P5 ...................................................................................................................................94 B.1 Test P6 .................................................................................................................................100 B.1 Test P7 .................................................................................................................................106 B.1 Test P8 .................................................................................................................................112 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 7 of 117 Index of Tables Table 2.1: Catalogue of the chemical species available in ECART...................................................24 Table 3.1: ICE tests P1 – P8 nominal boundary conditions...............................................................33 Table 4.1: Components of the ECART nodalisation..........................................................................35 Table 4.2: Connections in the nodalization........................................................................................36 Table 4.3: Actual experimental initial conditions used in the post-tests............................................39 Table 5.1: P1 – Experimental data vs. ECART results. .....................................................................40 Table 5.2: P2 – Experimental data vs. ECART results. .....................................................................43 Table 5.3: P3 – Experimental data vs. ECART results. .....................................................................46 Table 5.4: P4 – Experimental data vs. ECART results. .....................................................................48 Table 5.5: P5 – Experimental data vs. ECART results. .....................................................................50 Table 5.6: P6 – Experimental data vs. ECART results. .....................................................................52 Table 5.7: P7 – Experimental data vs. ECART results. .....................................................................55 Table 5.8: P8 – Experimental data vs. ECART results. .....................................................................57 Table B.1: Summary of the main results for the cases P1 – P8. ........................................................69 Index of Figures Figure 1.1: The upgraded ICE Facility...............................................................................................12 Figure 2.1: Schematic of the linking among the three main sections of ECART. .............................13 Figure 2.2: Control volume model adopted for ECART thermal-hydraulics. ...................................14 Figure 2.3: Aerosol and vapour transport phenomena simulated in each control volume.................18 Figure 2.4: Aerosol particle size distribution modelled by ECART at a given time. ........................19 Table 2.1: Catalogue of the chemical species available in ECART...................................................24 Figure 3.1: Major components of the upgraded ICE Facility. ...........................................................27 Figure 3.2: Appearance of the upgraded ICE Facility. ......................................................................28 Figure 3.3: Location of the points where the wall temperature was measured..................................30 Figure 3.4: Slit configuration at the divertor......................................................................................31 Table 3.1: ICE tests P1 – P8 nominal boundary conditions...............................................................33 Figure 4.1: ECART model of the upgraded ICE Facility. .................................................................34 Table 4.1: Components of the ECART nodalisation..........................................................................35 Table 4.2: Connections in the nodalization........................................................................................36 Table 4.3: Actual experimental initial conditions used in the post-tests............................................39 Table 5.1: P1 – Experimental data vs. ECART results. .....................................................................40 Table 5.2: P2 – Experimental data vs. ECART results. .....................................................................43 Table 5.3: P3 – Experimental data vs. ECART results. .....................................................................46 Table 5.4: P4 – Experimental data vs. ECART results. .....................................................................48 Table 5.5: P5 – Experimental data vs. ECART results. .....................................................................50 Table 5.6: P6 – Experimental data vs. ECART results. .....................................................................52 Figure 5.1: ICE P6 – Heat transfer coefficient for the PC. ................................................................53 Table 5.7: P7 – Experimental data vs. ECART results. .....................................................................55 Table 5.8: P8 – Experimental data vs. ECART results. .....................................................................57 Table B.1: Summary of the main results for the cases P1 – P8. ........................................................69 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 8 of 117 Figure B.1 ICE P1 – Flow rates. ........................................................................................................70 Figure B.0.2 ICE P1 – PC Pressure (short term)................................................................................70 Figure B.3 ICE P1 – PC Pressure.......................................................................................................71 Figure B.4 ICE P1 – VV Pressure......................................................................................................71 Figure B.5 ICE P1 – ST Pressure.......................................................................................................72 Figure B.6 ICE P1 – PC Atmosphere Temperature. ..........................................................................72 Figure B.7 ICE P1 – VV Atmosphere Temperature. .........................................................................73 Figure B.8 ICE P1 – PC Wall Temperature. ......................................................................................73 Figure B.9 ICE P1 – VV Wall Temperature. .....................................................................................74 Figure B.10 ICE P1 – DT Pressure. ...................................................................................................74 Figure B.11 ICE P1 – DT Atmosphere Temperature.........................................................................75 Figure B.12 ICE P2 – Flow rates. ......................................................................................................76 Figure B.13 ICE P2 – PC Pressure (short term).................................................................................76 Figure B.14 ICE P2 – PC Pressure.....................................................................................................77 Figure B.15 ICE P2 – VV Pressure....................................................................................................77 Figure B.16 ICE P2 – ST Pressure.....................................................................................................78 Figure B.17 ICE P2 – PC Atmosphere Temperature. ........................................................................78 Figure B.18 ICE P2 – VV Atmosphere Temperature. .......................................................................79 Figure B.19 ICE P2 – PC Wall Temperature. ....................................................................................79 Figure B.20 ICE P2 – VV Wall Temperature. ...................................................................................80 Figure B.21 ICE P2 – DT Pressure. ...................................................................................................80 Figure B.22 ICE P2 – DT Atmosphere Temperature.........................................................................81 Figure B.23 ICE P3 – Flow rates. ......................................................................................................82 Figure B.24 ICE P3 – PC Pressure (short term).................................................................................82 Figure B.25 ICE P3 – PC Pressure.....................................................................................................83 Figure B.26 ICE P3 – VV Pressure....................................................................................................83 Figure B.27 ICE P3 – ST Pressure.....................................................................................................84 Figure B.28 ICE P3 – PC Atmosphere Temperature. ........................................................................84 Figure B.29 ICE P3 – VV Atmosphere Temperature. .......................................................................85 Figure B.30 ICE P3 – PC Wall Temperature. ....................................................................................85 Figure B.31 ICE P3 – VV Wall Temperature. ...................................................................................86 Figure B.32 ICE P3 – DT Pressure. ...................................................................................................86 Figure B.33 ICE P3 – DT Atmosphere Temperature.........................................................................87 Figure B.34 ICE P4 – Flow rates. ......................................................................................................88 Figure B.35 ICE P4 – PC Pressure (short term).................................................................................88 Figure B.36 ICE P4 – PC Pressure.....................................................................................................89 Figure B.37 ICE P4 – VV Pressure....................................................................................................89 Figure B.38 ICE P4 – ST Pressure.....................................................................................................90 Figure B.39 ICE P4 – PC Atmosphere Temperature. ........................................................................90 Figure B.40 ICE P4 – VV Atmosphere Temperature. .......................................................................91 Figure B.41 ICE P4 – PC Wall Temperature. ....................................................................................91 Figure B.42 ICE P4 – VV Wall Temperature. ...................................................................................92 Figure B.43 ICE P4 – DT Pressure. ...................................................................................................92 Figure B.44 ICE P4 – DT Atmosphere Temperature.........................................................................93 Figure B.45 ICE P5 – Flow rates. ......................................................................................................94 Figure B.46 ICE P5 – PC Pressure (short term).................................................................................94 Figure B.47 ICE P5 – PC Pressure.....................................................................................................95 Figure B.48 ICE P5 – VV Pressure....................................................................................................95 Figure B.49 ICE P5 – ST Pressure.....................................................................................................96 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 9 of 117 Figure B.50 ICE P5 – PC Atmosphere Temperature. ........................................................................96 Figure B.51 ICE P5 – VV Atmosphere Temperature. .......................................................................97 Figure B.52 ICE P5 – PC Wall Temperature. ....................................................................................97 Figure B.53 ICE P5 – VV Wall Temperature. ...................................................................................98 Figure B.54 ICE P5 – DT Pressure. ...................................................................................................98 Figure B.55 ICE P5 – DT Atmosphere Temperature.........................................................................99 Figure B.56 ICE P6 – Flow rates. ....................................................................................................100 Figure B.57 ICE P6 – PC Pressure (short term)...............................................................................100 Figure B.58 ICE P6 – PC Pressure...................................................................................................101 Figure B.59 ICE P6 – VV Pressure..................................................................................................101 Figure B.60 ICE P6 – ST Pressure...................................................................................................102 Figure B.61 ICE P6 – PC Atmosphere Temperature. ......................................................................102 Figure B.62 ICE P6 – VV Atmosphere Temperature. .....................................................................103 Figure B.63 ICE P6 – PC Wall Temperature. ..................................................................................103 Figure B.64 ICE P6 – VV Wall Temperature. .................................................................................104 Figure B.65 ICE P6 – DT Pressure. .................................................................................................104 Figure B.66 ICE P6 – DT Atmosphere Temperature.......................................................................105 Figure B.67 ICE P7 – Flow rates. ....................................................................................................106 Figure B.68 ICE P7 – PC Pressure (short term)...............................................................................106 Figure B.69 ICE P7 – PC Pressure...................................................................................................107 Figure B.70 ICE P7 – VV Pressure..................................................................................................107 Figure B.71 ICE P7 – ST Pressure...................................................................................................108 Figure B.72 ICE P7 – PC Atmosphere Temperature. ......................................................................108 Figure B.73 ICE P7 – VV Atmosphere Temperature. .....................................................................109 Figure B.74 ICE P7 – PC Wall Temperature. ..................................................................................109 Figure B.75 ICE P7 – VV Wall Temperature. .................................................................................110 Figure B.76 ICE P7 – DT Pressure. .................................................................................................110 Figure B.77 ICE P7 – DT Atmosphere Temperature.......................................................................111 Figure B.78 ICE P8 – Flow rates. ....................................................................................................112 Figure B.79 ICE P8 – PC Pressure (short term)...............................................................................112 Figure B.80 ICE P8 – PC Pressure...................................................................................................113 Figure B.81 ICE P8 – VV Pressure..................................................................................................113 Figure B.82 ICE P8 – ST Pressure...................................................................................................114 Figure B.83 ICE P8 – PC Atmosphere Temperature. ......................................................................114 Figure B.84 ICE P8 – VV Atmosphere Temperature. .....................................................................115 Figure B.85 ICE P8 – PC Wall Temperature. ..................................................................................115 Figure B.86 ICE P8 – VV Wall Temperature. .................................................................................116 Figure B.87 ICE P8 – DT Pressure. .................................................................................................116 Figure B.88 ICE P8 – DT Atmosphere Temperature.......................................................................117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Acronyms AMMD AV CH DIMNP DT DV EdF ENEA EU EVITA HTC ICE ITER LWR NPP PC RCS RD RP SA ST TH VV Aerosol Mass Median Diameter Aerosol and Vapour Chemical Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione Drain Tank Divertor Electricité de France Ente per le Nuove Tecnologie l’Energia e l’Ambiente European Union Experimental Vacuum Ingress Test Apparatus Heat Transfer Coefficient Ingress of Coolant Event International Thermonuclear Experimental Reactor Light Water Reactor Nuclear Power Plant Plasma Chamber Reactor Cooling System Rupture Disk Relief Pipe Severe Accident Suppression Tank Thermal-Hydraulic Vacuum Vessel PAGE 10 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 11 of 117 1. INTRODUCTION This work is related to the application of the ENEL (now ) and EdF ECART (ENEL Code 1 for Analysis of Radionuclide Transport) code [Parozzi, 1997a and 1997b] on 8 thermal-hydraulic tests performed inside the upgraded [Takase, 2001a] Integrated ICE test facility (Figure 1.1), built by the JAERI in Naka laboratories (Japan). The new set of experimental tests (P1 - P8) has been scheduled and performed by JAERI during 2001, to assess the influence of the suppression tank connection (upper position, in the upgraded facility) and the presence of a drain tank on the reached maximum pressure [Topilski, 2003]. The main features of the ECART code will be described in this report, as far as the characteristics of the modified experimental facility ICE and the conditions for the 8 experiments. The combined effect of the jet impingement and heat transfer between the fluid and the walls have been studied too. Some of these effect are significant for ITER, some others play a very little role in ITER (jet impingement, for example) but they are significant to model correctly the behaviour of the ICE facility, as shown also in the previous DIMNP calculations for the former layout of the ICE device [Oriolo, 1998]. All the related geometrical data and the specific initially and boundary conditions for the analysis have been furnished to the DIMNP by ENEA Frascati Fusion Division [Porfiri, 2002], [Porfiri, 2003] while the ECART code was made available to ENEA Frascati and Pisa University by CESI Milan. The structure of the report is the following: 1 - the second chapter depicts the ECART code features; - the third chapter outlines the ICE facility; - the fourth chapter traces the nodalization adopted in ECART to model the ICE facility; - the fifth chapter reports the simulation results - the sixth chapter draws the conclusion of the validation work. CESI acquired at the end of 1999 the Research & Development division of ENEL. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 12 of 117 Figure 1.1: The upgraded ICE Facility. These activities have been carried out in the general framework of the ECART validation phase. The code was initially developed by ENEL and EdF for integrated analysis of SAs in LWRs. Afterwards it was applied on incidental sequences related to the ITER FEAT fusion plant. Main points of this validation phase for the thermal-hydraulic module were, in the past, the DIMNP activities related on the first Japanese ICE facility [Oriolo, 1998] and on the French EVITA experimental apparatus [Paci, 2000], always performed in the framework of research contracts between Pisa University and ENEA Frascati. Several campaigns for the validation of the computer codes to be utilised in safety analysis were performed in the ITER design frame (EFDA Task TW0-SEA 5A – Analysis verification) during the last years. So, a specific aim of these calculations is also to evaluate the capability of the ECART code to perform the accident analyses necessary for the safety reporting. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 13 of 117 2. MAIN CHARACTERISTICS OF THE ECART CODE 2.1 Main Features of the Code ECART is designed [Parozzi, 1997a and 1997b] to operate with three sections (Figure 2.1), linked together, but able to be activated also as stand-alone modules: a) thermal-hydraulic (th)- providing boundary conditions for chemistry and aerosol/vapour transport models; b) aerosol and vapour (av)- calculating the amount of radioactive or toxic substances that may be retained or released in the analyzed circuit components; c) chemical (ch) - chemical equilibrium among the compounds (only in vapour form) and reactions between gaseous phase and solid materials. Figure 2.1: Schematic of the linking among the three main sections of ECART. 1. 2. 3. 4. 5. thermal-hydraulic boundary conditions for chemical reactions quantity of each chemical compound in gaseous phase concentration of airborne reactants thermal-hydraulic boundary conditions for aerosol and vapours transport phenomena heat sources associated to transported species and aerosol concentrations capable to modify gas physical properties The code applies to pure transport phenomenology (mass, energy, momentum transfer and chemical processes) in whatever part of a given circuit. Support by other tools or experimental data can be used as boundary conditions or to account plant-dependent phenomena (e.g. releases from fuel, intervention of specific safety devices, etc.). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 14 of 117 The ECART structure is designed to treat the thermal-hydraulic phenomena and the aerosol/vapour transport in an arbitrary flow system that the user can arbitrarily subdivide into a series of control volumes connected by flow junctions, chosen on the basis of considerations regarding geometrical features, thermal-hydraulic conditions and/or the expected retention of aerosols and vapours. Other details of transport analysis can be also decided by the user, like the number of chemical species, the occurrence of agglomeration or other phenomena and the multicomponent description. Inside each control volume, a two-region model is adopted (Figure 2.2), being the liquid pool separated from the atmosphere. Within each region, thermal equilibrium is always assumed. Therefore, non-equilibrium effects related to superheated vapour injected in the pool or subcooled water sprayed in the atmosphere are separately accounted for. Figure 2.2: Control volume model adopted for ECART thermal-hydraulics. Aerosols are assumed to be well-mixed inside the volumes. This assumption requires that the amount of vapour and/or aerosol removed within the control volume is “small” in relation to the total amount of material transported throughout the control volume itself. A corrective action (called “plug” flow) is provided for those volumes, like a long pipe, having only a radial mixing (a concentration gradient exists along the pipe). The direction and the rate of the carrier flow can be directly assigned in input, together with other boundary data, or can be predicted by the DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 15 of 117 thermal-hydraulic section. This direction can change with time, although the aerosol transport through junctions is treated as one-dimensional (i.e. there is not simultaneous mixing through a junction). Two-dimensional flows, required to simulate scenarios where the natural convection streams could enhance the mixing among the volumes, can be accounted using two junctions to describe the exchanges between the two volumes. Recirculation phenomena or chimney-effects promoted by the injection of hot or lighter gas into large environments are taken into account by aerosol and vapour module, in the absence of any sub-nodalisation, through the estimate of a “recirculation velocity”. 2.1.1 Thermal-Hydraulic Models Basing on previous DIMNP experience in the development & application of models for analyzing thermal-hydraulics during postulated accidents and considering the peculiarities of the AV models, the following characteristics were established for the TH section: a) capability of describing TH accident transients in NPP circuits, with the degree of detail required by the AV section, and capability of processing incomplete experimental data providing the lacking information on local behaviour; b) transport simulation of the aerosol carrier gases expected within LWR plants under SA conditions and usually employed in experimental tests (steam, argon, helium, hydrogen, carbon dioxide, carbon monoxide, krypton, nitrogen, oxygen and xenon); c) solution of mass, energy and momentum balance equations in order to provide for realistic representations of fluid flow and heat transfer; d) calculation of pool levels in the control volumes and evaluation of steam suppression effects to support the aerosol scrubbing phenomenology; e) steam condensation modelled by splitting bulk and wall condensation (influencing, respectively, aerosol growth and aerosol diffusiophoretic deposition); f) allowance for counter-current flow conditions at junctions; g) capability of evaluating wall heat transfer taking into account wall thermal conductivity changes due to aerosol deposition and radioactive decay heat sources; Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 16 of 117 h) possibility of characterizing heat structure surfaces with local hydraulic parameters having strong influence on aerosol deposition and resuspension mechanisms (i.e. hydraulic diameter, local fluid velocity and Reynolds number, etc.). The assumption of complete stratification in a control volume is fairly well suited for containment analyses. It has some limitations in pipelines, but these limitations are accepted considering that, under SA conditions, single-phase flow (superheated steam-hydrogen mixture) or stratified flow (formation of water sumps in cold components) is likely to occur. A complete solution of the problem would require flow regime maps and constitutive laws for interfacial area and heat transfer under various regimes. However, this kind of accident scenarios, expected to be of minor importance in terms of Source Term (as a Steam Generator Tube Rupture), would imply removal mechanisms differing from those mainly influencing the Source Term associated to the SAs normally considered for probabilistic safety assessments. 2.1.1.1 Evaluation of Heat Transfer Coefficients The particular heat transfer regime applicable to the actual conditions is selected by ECART [Parozzi, 1997b] on the basis of various thermal-hydraulic parameters related to the heat transfer surface and the facing control volume. Pressure, fluid temperature and velocity, hydraulic diameter, fluid thermo-physical properties, wall temperature, etc., are the heat transfer package main input parameters, the output ones being the convective heat transfer coefficient and the heat flux. A full range of heat exchange phenomena is considered, although the need to develop a fast-running package required to adopt various simplifications, which are nevertheless consistent with the overall strategy adopted in setting up ECART. The criteria for choosing the heat transfer regime and the related correlation are based on the comparison of the wall temperature, the saturation temperature and the dew temperature with the actual fluid temperature value. Six different heat transfer modes are considered: 1. single-Phase Liquid Convection (natural or forced, laminar or turbulent); 2. boiling (subcooled and saturated); 3. transition Boiling; 4. film Boiling or Dispersed Flow Film Boiling; 5. single Phase Gas Convection (natural or forced); Associazione ENEA-EURATOM sulla Fusione 6. DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 17 of 117 condensation. As far as the evaluation of thermal-hydraulic parameters taken into account for heat exchange coefficient is concerned, the value of average volume pressure is considered, but void fraction, fluid temperature, enthalpy and thermo-physical properties are assigned considering the actual position of the structure in the volume with reference to the calculated liquid level; in particular, if the level separates the surface in two regions, facing the liquid and the gas respectively, an average fluid temperature and an heat transfer coefficient are evaluated for each region; these values are averaged considering the relative areas in order to obtain realistic values of the overall conductance. 2.1.2 Aerosol and Vapour Models Although ECART adopts the classic well-mixed assumption to describe the transport within each control volume, the vapour and particles deposition and resuspension phenomena can be described by dividing each control volume into sub-regions (normally, coincident with single heat structures or sumps), where local thermal-hydraulic conditions (temperature, gas flow velocity, etc.) can be taken into account. By this way, small components or devices can be analyzed as part of larger control volumes, with a unique run of the master aerosol equation and longer time steps. Within each control volume, all phenomena that can be responsible for retention or re-entrance of radioactive or toxic substances can be taken into account (Figure 2.3). 2.1.2.1 Transport of Volatile Substances Because of their negligible latent heat, condensation and evaporation of volatile species onto and from airborne particles and structure surfaces are dynamically calculated by diffusion equations. Conversely, steam-water phase changes can be either calculated by the TH module or assigned as input. The condensation and evaporation onto and from airborne particles promote aerosol growth or shrinkage, modify the two shape factors if necessary (see next paragraph) while the presence of a liquid phase in an aerosol deposit can inhibit its resuspension. Irreversible sorption of CsOH, I, I2, HI, Te and Te2 vapours onto wall surfaces (made by SS or nickel alloys) and airborne particles is also modelled by adopting experimentally based correlations. The experimentally determined vapour deposition velocities on hot surfaces may not represent an accurate description of the process as it occurs because of the imprecision in the available data [Parozzi, 1997b]. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 18 of 117 STEAM VAPORS DEPOSITION SURFACES PHYSICAL RESUSPENSION LAMINAR DEPOSITION TURBULENT DEPOSITION THERMOPHORESIS GRAVITATIONAL SETTLING WATER SUMP AEROSOL G R O W TH CENTRIFUGAL DEPOSITION DIFFUSIOPHORESIS SUM P BUBBLING AEROSOLS Figure 2.3: Aerosol and vapour transport phenomena simulated in each control volume. 2.1.2.2 Transport of Aerosol Particles ECART works with discretised size distributions (Figure 2.4), both for airborne and deposited particles, where the maximum number of the size bins is an input choice (default 20). Ordinary differential equations solvers, with implicit integration methods, allow saving computing time and preventing numerical instabilities. To compute the evolution of aerosol particles, mono-component basic aerosol equations can be used as default choice (i.e., at a given time, all the size bins in a given volume have the same composition). A multicomponent description of both airborne and deposited particles is possible optionally. This multicomponent approach (i.e., each size bin has its own composition), is obtained through an approximation: the aerosol and vapour module individually tracks the transported species in each size bin, accounting for sources, particle growths or shrinking, DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 19 of 117 depositions, resuspension, etc.. The correctness and the stability of this multicomponent approach were tested through virtual tests having a known solution. 8.E-09 0.6 AMMD 1.2 microns - GSD 2.0 7.E-09 Log-normal distribution mass concentration at time 0.0 0.5 0.4 5.E-09 4.E-09 0.3 3.E-09 0.2 Mass concentration [kg/m3] Log-Normal distribution [-] 6.E-09 2.E-09 0.1 1.E-09 0.0 0.E+00 0.007 0.012 0.021 0.037 0.067 0.119 0.211 0.375 0.667 1.186 Mean Radius [micron] 2.109 3.750 6.668 11.857 21.085 37.495 Figure 2.4: Aerosol particle size distribution modelled by ECART at a given time. The asphericity of aerosol or dust particles is simulated by input assigning two size-dependent shape factors: 1. “aerodynamic shape factor” χ, accounting for the different resistance to the motion of the actual particle if compared to the mass-equivalent sphere; 2. “collision shape factor” γ, accounting for the increased effective collision cross-section. The spherical shape is the code default for the particles (χ = 1.0 and γ = 1.0) but larger values for these two shape factors are normally present in LWR RCS conditions for “dry” particles [Parozzi, 1997b]. This spherical shape is however always assumed for “wet” particles, having an input given mass fraction of water (default 0.7), while the “dry factors are utilised if the liquid mass fraction is lesser than 0.2; for intermediate values a linear interpolation is performed. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 20 of 117 The agglomeration models are based on the calculation of “collision kernels” related to the different mechanisms for the agglomeration of the airborne particles. The collision frequency is then calculated multiplying this kernel by the aerosol concentration. Three processes of agglomeration are taken into account: i) Brownian (formula derived by Smoluchowski); ii) Gravitational (collision between particles having different settling velocities); iii) Turbulent, shear and inertial (Saffman and Turner’s formula). Particle growth due to bulk condensation of vapours and steam is modelled, also allowing the simulation of a possible hygroscopic behaviour of particles through the Van’t Hoff factor, characterising the hygroscopicity of the considered chemical species. The Kelvin effect is taken into account in the case of steam condensation, which is inhibited for particles having radii smaller than the critical radius calculated by the code. The deposition rate of the aerosol particles onto the different wall or pool surfaces is calculated as the sum of “deposition velocities” attributed to different effects: ¾ inertial impaction from turbulent flow (according to Liu-Agarwal observations); ¾ diffusion from turbulent flow (Davies’ formula); ¾ diffusion from laminar flow (Gormley-Kennedy’s formula); ¾ thermophoresis (Brock’s correlation with Talbot’s coefficients); ¾ gravitational settling (Stokesian and non-Stokesian regimes); ¾ centrifugation in curved pathways and pipe bends (Stokesian and non-Stokesian regimes; trapping in narrow bends); ¾ diffusiophoresis (Schmitt-Waldmann’s formula). The particle mechanical resuspension and the inhibition of their deposition, both caused by fast gas flows, is evaluated though an original semi-empirical approach based on a relationship between the acting forces on particles (adhesive and aerodynamic) and resuspension rates experimentally measured. This model takes into account both for the transient resuspension of already formed aerosol deposits and for the steady-state resuspension occurring in equilibrium with particle turbulent deposition. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 21 of 117 In water sumps, the possible particle scrubbing phenomena is modelled, accounting for the aerosol phenomena occurring within the rising bubbles: inward and condensing steam, gravitational settling, particle diffusion and centrifugation. 2.1.2.3 Coupling Between Aerosol and Thermal-Hydraulic Calculations In the case of a coupled run of aerosols and thermal-hydraulics, the AV section receives all the required data from TH, and gives a feedback to heat and mass transfer calculations. Then, the influence of high airborne aerosol concentrations on the gas physical properties (apparent density and viscosity) is taken into account. The coupling among the two sections is explicit: as the TH section and the AV section are advanced with their own convergence criteria, a proper logic of time step synchronization is adopted. The thermal-hydraulic problem is firstly solved over the time interval between two synchronous conditions (of the order of the lowest Courant limit in the nodalisation), often adopting short time steps, suitable for numerical explicit algorithms. The aerosol calculations follow, with implicit integration methods allowing time steps usually an order of magnitude longer than the thermal-hydraulics ones: this technique gives the possibility to smooth out the data related to flow rates and pressures calculated by the TH section in the case of oscillations due to limited instabilities. 2.1.3 Chemistry Models The CH section provides the AV section with the gaseous phase composition on the basis of equilibrium conditions. The chemical equilibrium calculation occurs whenever significant changes in temperatures, pressures or vapour species amount are calculated by the other two sections. Possible phase changes causing condensation onto walls and airborne particles, however, are dynamically accounted for in the diffusive model employed by the AV section. The solving algorithm is based on Gibbs free energy minimization at constant pressure and temperature of the system: this allows the calculation of the equilibrium composition of the mixture in terms of molar fractions. In order to manage the formation and evolution of radionuclide species within LWR Reactor Coolant Systems, this CH section is dimensioned for environments characterized by temperatures in the range from room conditions up to 2,500. K, with pressures up to 15. MPa. Real gas behaviour is modelled by fugacity coefficients computed according to Redlich-Kwong-Soave equation for a hydrogen-steam mixture. The code uses a Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 22 of 117 non-linear minimization algorithm preventing the linearization of the function to be minimized, which would affect the correctness of final results. The possible reactants and reaction products considered (Table 2.1) are the carrier gas components, with the exception of nitrogen and noble gases, and most of the species which can be transported in form of vapours. To match with the phase changes calculated by the AV section, super saturation conditions of the predicted vapours are accepted by chemistry algorithms. The databases contained in chemical section are also used to determine the temperature-dependent saturation pressures of all volatile species. The CH section contains information about the most representative compounds for a LWR SA sequence. Further compounds, involved in fusion reactor safety problems, are also included in the catalogue (Table 2.1) as discussed in the next paragraph. 2.1.3.1 Models for Chemical Reactions in Fusion Reactor Accidents ECART allows fitting the fusion reactors model for the oxidation reactions of beryllium, graphite and tungsten in air and steam. These reactions involve three features modelled by the code: heat structures, aerosol particles suspended in the carrier gas and aerosol particles deposited on walls. The reactions of beryllium, graphite and tungsten solid walls of PFCs or dusts with air and/or steam are not explicitly treated by the chemical section of ECART but in a separate ad-hoc module which makes use of surface reactions rates computed by means of semi-empirical correlations, also giving the reaction heats released to or removed from the environment. The oxidation reactions are only limited by the availability of steam and oxygen in the carrier gas, while the mass of the reacting element (Be, C or W) in the suspended or deposited aerosol cannot become negative (on a solid wall, the reacted elements Be, C and W and the solid oxide reaction products BeO and WO3 are not accounted for). If the amount of steam or oxygen required by all the reactions occurring concurrently, in the current time step, is greater than the available mass, the ∆m of each reaction is scaled by the ratio of the available to the required mass of steam or oxygen. In this way, no reaction is favoured but some delay in the reaction completion could result. Obviously, in a stand-alone aerosol-vapour analysis, no account is taken of the reaction heating and of the mass addition to or subtraction from the carrier gas because the thermal-hydraulic Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 23 of 117 conditions are fixed by input tables. On the contrary, for the reactions occurring in the suspended or deposited aerosol, the mass increase (or decrease) in a time step or sub-step, of the involved chemical species (e.g., Be and BeO) is allowed for in the mass balance equations and is distributed over the aerosol size bins proportionally to the square of the geometric mean radius of the particles. If a thermal-hydraulics/aerosol-vapour coupled analysis is performed, the reaction heat (positive for exothermic reaction) is added to the gas atmosphere for reactions occurring in the suspended aerosol and is added to the structure for reactions occurring on the solid surface or in the deposited aerosol. The masses of the carrier gas components (steam, hydrogen, oxygen, carbon monoxide and dioxide) released or removed by the reactions, as well as the correspondent enthalpies, are accounted for in thermal-hydraulics. The reactions in the suspended aerosol are assumed to occur at the gas bulk temperature, while the boundary layer temperature (i.e. geometric mean of wall and gas bulk temperatures) is used for the reactions with solid walls and deposited aerosols. This last assumption is questionable and it is under further assessment (at the present, in the code input deck is possible to choose the temperature to be used – bulk or wall). The reaction area is identified with the wall surface area for the reactions on a solid wall and with the surface area of all the particles multiplied by the mass fraction of the reacted element for the reactions in the airborne aerosol. Also, as far as the reaction area for the deposited aerosol is concerned, the total surface area of the aerosol particles is assumed except when the deposited liquid mass exceeds a given fraction of the total deposited mass, in which case the area of the underlying wall is assumed. However, for a multi-layer deposited aerosol, the basic reaction area should be reduced depending on the depth of the deposited aerosol and on the dispersion (standard deviation) of the aerosol particles distribution, i.e., on the compactness of the aerosol agglomerate. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 24 of 117 Table 2.1: Catalogue of the chemical species available in ECART. Species Name Species Description Normal melting point [K] Normal boiling Point [K] Ag AgI B BI3 B2O3 Ba BaI BaI2 BaO BaOH Ba(OH)2 Be BeO C Cd CdI CdI2 CdO Cd(OH)2 CdTe CH4 Co Cr CrI CrI2 CrO Cr2O3 Cs CsBO2 CsI CsO CsOH Cs2 Cs2CrO4 Cs2MoO4 Cs2O Cs2(OH)2 Cs2Te Cs2TeO3 Cs2ZrO3 Cu CuO D D2 Silver silver iodide Boron boron triiodide boron sesquioxide Barium Barium monoiodide Barium iodide Barium oxide Barium hydroxide Barium dihydroxide Beryllium Beryllium oxide Carbon cadmium cadmium monoiodide cadmium diiodide cadmium oxide cadmium dihydroxide cadmium telluride methane cobalt chromium chromium monoiodide chromium diiodide chromium oxide chromium sesquioxide Caesium Caesium borate Caesium iodide Caesium monoxide Caesium hydroxide diatomic caesium Caesium chromate Caesium molybdate Caesium oxide Caesium dihydroxide Caesium telluride Caesium tellurite Caesium zirconate copper Copper monoxide Elemental deuterium molecular deuterium 1234. 831. 2350. 323 723. 1000. -984. 2286. -681. 1560. 2821. 3925. 594. -660. --1314. -1768. 2130. -1129. -2603. 301.5 -900. -500. --763. ----1358 1599 --- 2436. 1779. 4139 483 2133. 2119. -2337. --1325. 2741. -5100. 1038. -1069. ----3198. 2945. ---4273. 948. -1553. -1263. --763. ----2843 2073 --- Solid density [kg/m3] 10500 5683 2355 3350 2460 3510 -5150 5720 -2180 1850 3010 2250 8642 -5670 6950 4790 6200 -8900 7200 -5196 -5210 1878 -4510 -3675 -4237 1000 4250 --1000 1000 8920 6400 --- Liquid density [kg/m3] 9320 4830 2080 3350 2090 3081 -4380 4862 -1850 1500 2258 1912 7530 -4820 5900 4070 5270 -7670 6460 -4417 -4430 1468 -4057 -3308 -4237 0850 3610 --0850 0850 7950 5440 --- Evaporat. / Condens. Chemisorption Yes Yes Yes No Yes Yes No Yes Yes No Yes Yes no no yes no yes yes no no no yes yes no yes no no yes no yes no yes no no yes yes no no no no yes yes no no No No No No No No No No No No No No(3) No(3) No(3) No No No No No No No No No No No No No No No No No sorbable(1) No No No No No No No No No No No No Associazione ENEA-EURATOM sulla Fusione Species Name Fe FeI2 FeO Fe2I4 Fe2NiO4 Fe2O3 Fe3O4 H HBO2 HI H2O H2Te H3BO3 I I2 In InI InTe In2O In2O3 In2Te Li2O LiOH Mn MnI2 MnO Mn2O3 Mn3O4 MoO2 MoO3 Ni Ni(CO)4 NiI2 NiO O OH RbI RbOH Ru RuO2 RuO3 Sb SbTe Sb2 Sb2O3 Sb2Te3 Species Description Normal melting point [K] Normal boiling Point [K] Iron iron iodide iron oxide iron iodide diiron nickel tetraoxide iron sesquioxide iron tetraoxide elemental hydrogen boric acid hydrogen iodide water hydrogen telluride boric acid elemental iodine molecular iodine indium indium monoiodide indium telluride indium suboxide indium sesquioxide diindium telluride Lithium oxide Lithium hydroxide manganese manganese diiodide manganese oxide manganese sesquioxide trimanganese tetraoxide molybdenum dioxide molybdenum trioxide nickel nickel carbonyl nickel iodide nickel monoxide elemental oxygen hydroxyl rubidium iodide rubidium hydroxide ruthenium ruthenium dioxide ruthenium trioxide antimony antimony monotelluride diatomic antimony antimony trioxide antimony tritelluride 1809. 1650. --1838. 1870. ---273. ---387. 430. 624 342. ---1843. 744. 1517. 911. 2115. -1835. -1075 1726 248 1070. 2263 --929.00 574. 2523. --904. --939. 902. 3132. 3687. ---1870. ---373. ---458. 2353. 986 ----2836 1897 2332 ---1835. -1428 3005. 316 ------4173. --2023. --1823. -- DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Solid density [kg/m3] 7860 5320 5700 --5240 5180 ---1000 ---4930 7300 5310 6290 6990 7179 -2013 1460 7200 5000 5445 4500 4856 6470 4692 8900 1320 5834 6670 --3550 3203 12300 6970 -6684 -5670 6500 Liquid density [kg/m3] 7020 4522 4840 --4450 4400 ---1000 ---4930 5585 4514 6290 6990 6100 -1711 1241 6430 4250 4630 3820 4130 5500 3988 7780 1320 4960 5700 --2870 2723 10900 5920 -5681 -4820 5525 PAGE 25 of 117 Evaporat. / Condens. Chemisorption Yes yes yes no no no no no no no yes no no no yes yes yes no no no no yes yes Yes No No No No Yes Yes Yes No No Yes No No Yes No Yes No No Yes No no no no sorber(2) No No No No No No No No Yes No No No Sorbable Sorbable No No No No No No No No No No No No No No No Sorber(2) No No No No No No No No No No No No No No No Associazione ENEA-EURATOM sulla Fusione Species Name Sb4 Sn SnH4 SnI2 SnO SnO2 SnTe Sr SrI2 SrO SrOH Sr(OH)2 T T2 Te TeO2 Te2 W WO3 Zn ZnO ZrI4 ZrO2 &... (1) (2) (3) (4) Species Description Normal melting point [K] Normal boiling Point [K] tetra atomic antimony tin tin tetrahydride tin iodide tin monoxide tin dioxide tin monotelluride strontium strontium iodide strontium oxide strontium hydroxide strontium dihydroxide Elemental tritium molecular tritium Tellurium tellurium dioxide diatomic tellurium Tungsten Tungsten trioxide Zinc zinc oxide Zirconium tetraiodide zirconium dioxide inert species(4) -505. -593. -1400. 1079. 1050. 811. 2938. -783. --723. 1006. -3680. 1745. 693. 2248. 772. 2950. Input -2873. -990. -2073. -1685. 2178. 3273. -1017 --1327. 1518. -5931 2110 1179. --4544. -- DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Solid density [kg/m3] -7280 -5290 6446 6950 6480 2600 4549 4700 -3625 --6250 5790 -19350 7160 7140 5606 1000 5890 input Liquid density [kg/m3] -7000 -4497 5448 5910 5510 2210 3870 3990 -3080 --5489 4920 -17600 6086 6570 4770 1000 5010 Input PAGE 26 of 117 Evaporat. / Condens. Chemisorption no yes no yes yes no yes yes yes no no yes no no yes yes no yes yes yes no yes yes no No No No No No No No No No No No No No No sorbable(1) No sorbable(1) No(3) No(3) No No No No No Also chemisorbable on steel wall and aerosol particles if Fe and/or Ni are present Also sorber for chemisorption in aerosol particles Involved in oxidation reactions with steam and oxygen Inert as aerosol, not requiring chemical equilibrium or phase change calculation, input added by user DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 27 of 117 3. INTEGRATED ICE TEST FACILITY DESCRIPTION The ICE facility was constructed at the Naka Laboratories of the Japan Atomic Energy Research Institute (JAERI) as part of the ITER program to obtain experimental data on the effectiveness of the ITER suppression system [Takase, 2001b]. The upgraded ICE test facility represents a 1/1600-scale model of ITER. A schematic of the major components of the facility is illustrated in Figure 3.1 and Figure 3.2. It includes a boiler (not represented in the figure) and four main volumes: the plasma chamber (PC), the vacuum vessel (VV), a drain tank (DT) and the suppression tank (ST). A small volume connects the PC to the VV and in this volume is located the simulated divertor (SD). 80 mm No.2 No.1 2100 mm Slit Plasma chamber (0.6 m 3) φ Water Relief pipe No.1 No.2 120 mm Nozzle 1200 mm φ 500 mm Nozzle Plate Divertor Slit 162 mm Nozzle Nozzle 1720 mm Magnet valve Nozzle 5 mm No.3 120 mm Nozzle 15 mm 600 mm Water injection nozzle 1200 mm No.3 Magnet valve Water injection nozzle 100 mm Relief pipe A Vacuum vessel (0.34 m 3) Divertor slit configuration Magnet valve Relief pipe Drain pipe B B φ 800 mm (0.4 m 3 ) Section A-A Suppression tank (0.93 m 3) Water (0.5 m 3) 1960 mm Drain tank Relief pipe No.3 No.1 No.2 Water SectionB-B A Figure 3.1: Major components of the upgraded ICE Facility. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 28 of 117 Three relief pipes Boiler Plasma chamber Divertor Vacuum pump Vacuum vessel Drain line Drain tank Suppression tank Figure 3.2: Appearance of the upgraded ICE Facility. 3.1 ICE Main Components 3.1.1 Boiler Connected to the plasma chamber by three injection lines (each with an internal diameter of 10 mm) is a pressurized boiler (not shown in Figure 3.1). This boiler supplies the water simulating the primary coolant. It consists of a cylindrical stainless steel tank with a diameter of 700 mm and 1800 mm long (the volume is about 0.631 m3). The maximum water volume stored in the boiler is about 0.2 m3 and can be heated to 250 °C by electrical heaters located in the boiler yielding a maximum saturation pressure of 3.97 MPa. The outlets of the injection lines are located on the bottom of the boiler. The three injection lines run from the bottom of the boiler and connect to the side of the plasma chamber. The lines are evenly spaced in the longitudinal direction. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 29 of 117 During the injection phase of the ICE transient the pressure in the boiler is maintained at the desired boiler pressure by high pressure nitrogen gas, in order to maintain a constant mass flow to the plasma chamber. A flow control valve located between a high-pressure nitrogen tank and the boiler is used to control the pressure in the boiler. 3.1.2 Plasma Chamber The ITER plasma chamber (PC) is represented by a cylindrical stainless steel tank with a diameter of 600 mm and 2100 mm long (its free volume is about 0.59 m3). The chamber wall, having a thickness of 10 mm are covered with a thick layer of insulation and can be heated to a specified temperature with electrical heaters. The maximum wall temperature is set at 250°C to cover the specified range in the VV of ITER. The maximum pressure of the plasma chamber is 1 MPa that is twice the design pressure of ITER (0.5 MPa). The SS wall temperature is controlled by several thermocouples. The positions of the experimental signals chosen in [Topilski, 2003] for the comparison with calculated data are indicated in the following Figure 3.3 3.1.3 Simplified Vacuum Vessel The ITER vacuum vessel (VV) is simulated by another cylindrical stainless steel tank with a diameter of 500 mm and a length of 1720 mm (free volume about 0.34 m3). In particular, this vacuum vessel simulates the bottom part of the vacuum vessel in ITER. The stainless steel tank again has a wall thickness of 10 mm, it is covered with a thick layer of insulation and can be heated to a specified temperature with electrical heaters. The maximum pressure and wall temperatures are 1 MPa and 250 °C, respectively. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 30 of 117 TPW-7 PC 0 TPW-7 TPW-26 45 TPW-26 Nozzle TPW-18 TPW-18 TVW-9 TVW-15 VV TVW-9 TVW-15 TVW-4 TVW-4 Figure 3.3: Location of the points where the wall temperature was measured. (the channel TVW-9 has been substituted by the channel TVW-8 for acquisition problems) 3.1.4 Divertor Orifice Plate A channel-like structure connects the vacuum vessel to the plasma chamber. It is made by insulated stainless steel and representing the ITER divertor (DV). The channel is 162 mm high, 120 mm wide, and has a length of 1200 mm. The bottom section of the channel contains a removable stainless steel plate with multiple slits that represents the ITER divertor pumping slots. The plate is approximately 120 mm wide, 1200 mm long and 15 mm thick. The plate was made removable so that the effects of the number of slits and their spacing on the pressurization of the PC and VV could be experimentally evaluated. The slits for this plate (Figure 3.4) are 5 mm wide, 80 mm long (in circumferential direction) and 15 mm in depth, i.e. the thickness of the plate. The slits were spaced on center 100 mm apart, with the first and last slit spaced 50 mm from the ends of the cylinder. All the ICE P1 – P8 experiments were run with a plate having four slits. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 31 of 117 3.1.5 Drain Tank The drain tank (DT) is a horizontal cylindrical volume of about 0.383 m3 with an inner diameter of 590 mm. No water is present inside this drain tank at the beginning of the tests. The drain tank is connected to the bottom part of the vacuum vessel by a drain line with an inner diameter of 16.1 mm. A magnetic valve is located just downstream from the vacuum vessel in the drain line. This valve has a set point of 0.11 MPa. Figure 3.4: Slit configuration at the divertor. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 32 of 117 3.1.6 Suppression Tank The last major component of the ICE facility is the stainless steel suppression tank (ST), which is used to control the maximum pressure the plasma chamber can experience. This suppression tank is a vertical cylindrical vessel with a diameter of 800 mm and a length of 1960 mm. The free volume is slightly less (~0.93 m3) due to the presence of the relief pipe, which couples the plasma chamber to the lower region of the suppression tank and of the two organ pipes that branch off the relief pipe, as shown in Figure 3.1 (inner diameter 800 mm). The suppression tank is connected with the upper part of the plasma chamber by three relief pipes with an inner diameter of 35.5 mm. Before each experimental ICE run, it contains approximately 0.4 m3 of subcooled water. The water temperature is set to be about 20 °C and 2300 Pa in order to condense the steam that flows from the vacuum vessel to the suppression tank, thus controlling the maximum pressure that the plasma chamber and vacuum vessel will experience. 3.2 Test Protocol The experimental transient is initiated when high pressure saturated water from the boiler is injected into the initially low pressure (~ 500 Pa) plasma chamber. Here some of the water immediately flashes to steam and the remaining water in the jets issuing from the injection nozzles impinges on the plasma chamber wall opposite the nozzles. As the water impinges on the wall, it is dispersed circumferentially and longitudinally around the plasma chamber wall adjacent to the impingement location. The dispersion produces additional steam due to film and/or nucleate boiling, depending on the wall surface temperature. This generation of steam adds to the steam already present from flashing causing the pressure in the plasma chamber and vacuum vessel to rapidly increase. A magnetic valve (representing rupture disks in the ITER relief piping) is located just downstream from the PC in the relief piping (RP). This valve has a set point of 0.15 MPa. It opens and relieves the pressure in the plasma chamber and vacuum vessel, depending on how efficiently the suppression tank condenses the high temperature vapour flowing from the PC. The nominal boundary conditions of the eight cases P1 – P8 are summarized in the following Table 3.1. DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 33 of 117 Table 3.1: ICE tests P1 – P8 nominal boundary conditions. No. P1 P2 P3 P4 P5 P6 P7 P8 No. RP Nozzles / diameter 3 3 / 7.3 mm 3 3 / 7.3 mm 3 3 / 7.3 mm 3 3 / 7.3 mm 1 3 / 7.3 mm 1 ½ mm 1 ½ mm 1 3 / 2 mm PC Temp (°C) 230 230 230 230 230 230 230 230 VV Temp (°C) 230 100 100 100 100 210 100 100 Div Temp (°C) 230 150 150 150 140 210 150 150 Injection time (s) 45 45 45 45 45 600 600 200 Boiler Temp (°C) 150 150 125 125 125 230 125 125 Boiler Press (MPa) 2 2 3 2 2 4 2 2 ST Water Temp (°C) 22 21 18 19 15 23 22 21 In all the tests the PC-VV flow area is 1.6 10-3 m2 (4 divertor slits). The set points for the opening of the relief pipe and drain pipe valves are 0.15 MPa and 0.11 MPa respectively. The injection time is 45 s for tests P1 to P5 (3 large nozzles), 600 s for tests P6 and P7 (1 small nozzle) and 200 s for the test P8 (3 small nozzles). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 34 of 117 4. INPUT ASSUMPTIONS The ECART code in its version 2K has been utilised to model the thermal-hydraulics behaviour of thee upgraded ICE facility. The code nodalization (Figure 4.1) represents the facility using the components reported in the Table 4.1. Boiler Line to ST Relief Pipe Plasma Chamber Rupture Disk Divertor Vacuum Vessel Drain Line Suppression Tank Control node Water pool Drain Tank Junction Figure 4.1: ECART model of the upgraded ICE Facility. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 35 of 117 The main sources for the nodalisation data have been the two ENEA FUS reports [Caruso, 2002] and [Meloni, 2002], related to the post tests analysis of the same ICE tests carried out respectively with CONSEN and INTRA codes. 4.1 Control Nodes In the ECART input deck, reported in Appendix A for the test P1, five control volumes have been utilised: PC (modelled with only one node, internally subdivided into the classical ECART regions, atmosphere and sump), VV (same criterion - only one single control node), ST (one node with an atmosphere zone of 0.1 m3 connected to a sump zone of 0.83 m3, DT (atmosphere zone only) and, finally, the node PBOIL representing the pipe between the back environment, schematizing the boiler, and the PC (this control volume is necessary because in ECART it is not possible to use a back environment volume coupled with an explicit junction as the one simulating the rupture disk). The back environment BOILER has an input imposed pressure and temperature time dependent history. Component Control nodes Back environment Implicit junctions Explicit junctions Heat structures Material Power tables No. 5 1 2 4 7 1 3 Table 4.1: Components of the ECART nodalisation. 4.2 Junctions The connections between the different zones of the ICE upgraded facility are modelled by two implicit junctions and by four explicit junctions (also called “spill & fill”), as reported in the Table 4.2, to take into account the exchange of air/ steam between the zones and the drainage for the water flow. “Choked” flow conditions are possible only for the explicit junctions [Parozzi, 1997 b], leading to the necessity of the PBOIL control volumes. Associazione ENEA-EURATOM sulla Fusione No. 1 2 3 4 5 6 Name BOPIPE DIV INJECT RDST RDDT RDDT2 From Boiler PC PBOIL PC VV PC DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 To PBOIL VV PC ST DT DT Type Implicit Implicit Explicit Explicit Explicit Explicit PAGE 36 of 117 Note Injection RD RD RD Table 4.2: Connections in the nodalization. About the explicit junction characteristics, one rupture disk junction RDST is located between the PC upper atmosphere zone and the sump zone in the ST (explicit junction No. 4). This rupture disk opens when the pressure in the PC rises up 0.15 MPa. The pressure drop coefficients in the RDST outlet have been tuned. They are the same for tests P1, P2, P3 and P4 and they are higher for the tests P5, P6, P7 and P8 due to the reduced number of the relief pipes towards the ST [Porfiri, 2004] (1 pipe vs. 3 pipes) and the consequent higher turbulence in the steam discharge [Takase, 2002]. A time delay in opening the RDST valve has been introduced: the ECART post test calculations have been performed introducing the real opening time inferred from experimental data file [Porfiri, 2002]. As a matter of fact in the experiments a delay was detected in the rupture disk opening if it is compared to the peak of pressure in the plasma chamber. This delay can affect strongly the maximum pressure reached in the PC and VV volumes. Another rupture disk junction RDDT is located between the VV sump zone and the atmosphere zone in the DT (explicit junction No. 5). This rupture disk opens when the pressure in the PC rises up 0.11 MPa but the ECART post test calculations have been performed introducing the real opening time inferred from experimental data file. There is also a spillage junction RDDT2 (No. 6) between the PC sump and the DT atmosphere zone to better discharge water, with the same opening set-point. The cross section of the rupture disk junction RDDT represents about 20% of the total area of the pipe in all the cases. The remaining 80% is assigned to the second spillage RDDT2 junction. As a matter of fact a part of the total amount of water flows through the divertor slits to the drain tank, without any significant interaction with the vacuum vessel volume. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 37 of 117 4.3 Heat Transfer Structures The seven heat transfer structures considered inside the ECART input deck have the following geometrical characteristics (they are all made by stainless steel): plasma chamber: PCWALL - cylindrical, 10 mm thick, externally insulated, with an internal surface of 3.313 m2. This structure is the main “target” for the jet impingement simulation. FLNPC - a second plate, simulating the PC flanges, is 0.5654 m2, 6 cm thick, externally insulated. DV - the third structures, located in the bottom of the PC to evaluate the simulating divertor, is a plate 1.2 cm thick, with an area of 0.662 m2, down facing also the VV atmosphere. vacuum vessel: VVWALL - cylindrical, 10 mm thick, externally insulated, with an internal surface of 2.71 m2. FLNVV - a plate simulating the VV flanges, 0.3928 m2, 6 cm thick, externally insulated. suppression tank: STWALL - cylindrical, 1.0 cm thick and 5.04 m2 of external surface, without any external insulation. drain tank: DTWALL - cylindrical, 1.0 cm thick and 3.0 m2 of external surface, without any external insulation. Three electric heaters warm up respectively the structures PCWALL, VVWALL and DV according to the power tables specified in [Porfiri, 2003] for the different cases, to maintain constant the wall temperatures. The temperature control system is simulated as a power density generation inside the three stainless steel masses. This heating system has not been included into the flanges. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 38 of 117 As code design choice, the correlations for the determination of the heat transfer coefficients between the control node atmosphere/sump and the different heat structures present inside the ICE facility are not chosen by the code user, as it is possible in other computer tools [Topilski, 2003], but are automatically selected by ECART on the basis of various thermal-hydraulic parameters related to the heat transfer surface and the facing control volume as described in Paragraph 2.1.1.1. Practically, there is a very small user’s influence on this choice and a limitation of the possibility to fully simulate particular phenomena; the unique input parameter that the user is free to force is the structure elevation inside the control volume, forcing in this way the structure presence inside the lower sump (i.e., heat exchange with the water separated from the blow-down jet and instantaneously separated in the lower part of the control volume). This is the choice adopted, inside the ICE nodalisation, for the hot structure PCWALL, forced inside the PC sump to partially simulate the jet impingement phenomenon caused by the water blow-down and, in the same way, to increase the steam production for the contact of the sump water with a hot structure, as carried out in the previous ICE calculations [Oriolo, 1998]. Also the upper surface of the structure DV has been simulated completely submerged inside the PC sump while its lower surface is in contact with the VV atmosphere. The other five heat structures, on the contrary, have their real vertical elevation inside the relative control volumes, exchanging with the atmosphere or the sump as a function of the predicted water level. 4.4 Boundary Conditions The actual experimental conditions, transmitted as a MS Excel© file in [Porfiri, 2002] and summarised in Table 4.3, are slightly different from the conditions utilised in [Caruso, 2002] and [Meloni, 2002] due to the difficulties to reach all the experimental conditions fixed in the test matrix at the same time. The ICE real experimental data have been utilized to initialize the eight ECART input decks, in order to take into account the differences between the desired experimental conditions, reported in Table 3.1, and those that was possible to acquire in the eight ICE tests. So, all the specified conditions have been considered according to the experimental data reported in electronic form [Porfiri, 2002]. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 39 of 117 Case P1 P2 P3 P4 P5 P6 P7 P8 PC temp (°C) 228 210 205 205 210 226 215 211 PC pressure (Pa) 1000 1000 1000 1000 1900 1000 1000 1000 DV temp (°C) 230 160 162 154 162 215 163 170 VV temp (°C) 227 120 110 105 116 210 121 125 VV pressure (Pa) 1000 1000 1000 1000 1900 1000 1000 1000 22 20 21 16 16 24 21 21 ST pressure (Pa) 3000 2300 2500 2600 4500 3400 2800 2400 Water in ST (kg) 700 700 500 700 700 500 500 700 DT temperature (°C) 19 19 18 16 20 20 21 19 3300 3200 3200 4300 5300 2800 3700 3200 ST temp (°C) DT pressure (Pa) Table 4.3: Actual experimental initial conditions used in the post-tests. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 40 of 117 5. RESULTS FROM CALCULATIONS OF ICE P1-P8 TESTS 5.1 ICE CASE P1 5.1.1 Main results The following Table 5.1 summarizes the comparison between the ECART post test calculations and the P1 experimental data. P1 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 2 s 372 kPa 2s 2. s 58.9 kPa 58.5 kPa 37.3 kPa 48.2 kPa ECART t = 2.5 s 371 kPa 2.5 s (imposed) 2.5 s (imposed) 37.6 kPa 38.3 kPa 28.2 kPa 36.4 kPa Table 5.1: P1 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.1 to Figure B.11, compared with the experimental trends and in Table B.1. 5.1.2 Analysis of the results In the case P1 the calculated flow rate of the water mass entering into the PC (Figure B.1) was in good agreement with the experimental data. This result is true also for all the other seven ICE tests and it is due to the use, in the ECART input deck, of a “back environment” for the simulation of the boiler, with the experimental pressure trend utilised as input datum, together with the time history of the temperature of the boiler water. The calculated pressure peaks in the PC (Figure B.0.2 and Figure B.3) and in the VV (Figure B.4) present a small delay of about 0.5 s respect to the experimental data but a very good agreement on the values of the peaks. These good results are due to the delay opening of 2.5 s for the DT and ST rupture disks (reference signals were 0.11 and 0.15 MPa in VV) imposed in the ECART simulation on the basis of the P1 real experimental conditions (i.e., the measured rupture disk intervention is delayed of about two seconds from the achievement of the reference pressure Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 41 of 117 set point). As a consequence of this time delay, the initial pressurisation phase is longer and the peak of the PC pressure reached in the code simulation is in very good agreement with the experimental one. From this initial pressure peak to the end of the water injection period (at 45 s) the pressure curves calculated by the code follow accurately the experimental ones, while an underestimation is present in the long term phase of the P1 test, probably due to a too high mass flow-rate calculated towards the ST (Figure B.1). In fact, the ST pressure curve (Figure B.5) is in very good agreement with the experimental signal during the initial injection phase and the following period (about 150 s) but in the long term worsens. The prediction of the condensation of the steam inside the ST pool is accurate enough for the simulation of the injection phase, with a high mass flow-rate, but the characterisation of the last phase of the transient is questionable, probably linked to a non correct schematisation of the vent pipes geometry inside the ST and of the real initial ST water level. The simulated atmosphere temperature in the PC (reported inside Figure B.6) follows correctly the temperature decrease due to the cold water inlet, apart some numerical oscillations. On the contrary for the temperature of the VV atmosphere (Figure B.7), different phases in the ECART simulation are present, with a different agreement with the experimental data: a) strong temperature peak predicted by ECART due to a compression effect in the first seconds of the VV transient, not present in the experimental data that immediately (in about 1 s) shift towards the saturation temperature value; b) presence of a slow atmosphere temperature increase in the experimental signals during the first 150 s of the test, phenomena followed quite well by the ECART simulation; c) probably wetting by liquid drops and/or rivulets of the thermocouples in the long term phase, where there is no difference between the experimental signals and the calculated results for the saturation temperature (i.e. the water temperature). The heat structure temperatures in the PC and in VV (respectively reported in Figure B.8 and Figure B.9) are in good agreement with the experimental walls’ temperatures during the phase of the water injection, when the “jet impingement” is the driving phenomenon (only partially simulated by ECART using a zero structure elevation as previously discussed in Paragraph 4.3). After the flow discharge interval, the differences between calculated and experimental results become sometimes significant (about 10 – 20 °C). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 42 of 117 The calculated pressure in the DT (Figure B.10) has a peculiar trend, always present also in the other ECART simulations of these ICE tests, that approximates the experimental results with an initial compression phase, not measured in the experiment. In the long term phase the pressure values are on the contrary similar between the code prediction and the experiment, also if the pressurisation rate is slower for the code. This good agreement is particularly true for the DT atmosphere temperature (Figure B.11). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 43 of 117 5.2 ICE CASE P2 5.2.1 Main results The following Table 5.2 summarizes the comparison between the ECART post test calculations and the P2 experimental data. The main difference respect to the previous test P1 is the lower initial value of the temperature of the VV atmosphere. P2 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 2 s 271 kPa 2s 2s 40.9 kPa 38.2 kPa 32.2 kPa 31 kPa ECART t = 2.5 s 288 kPa 2 s (imposed) 2 s (imposed) 34.2 kPa 35.1 kPa 26.5 kPa 33.0 kPa Table 5.2: P2 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.12 to Figure B.22, compared with the experimental trends and in Table B.1. 5.2.2 Analysis of the results The water flow rate injected inside the PC (Figure B.12) is in very good agreement with the experimental data for the reasons previously exposed for the ICE test P1. So, in the following of the present report, this consideration on the ECART good prediction of the injection flow-rate will not be repeated. The simulated PC pressure (Figure B.13 and Figure B.14) is on time respect the experimental pressure for the cause explained for the previous case P1 (imposed opening time of the ST and DT rupture disks), and also the value of the pressure peak is quite good respect to the experimental one. Again the long term behaviour shows the little overestimation of the mass flow towards the ST (Figure B.16). The VV total pressure (Figure B.15) is slightly overestimated by the code simulation; this could be due to the ECART modelling of the junction between the PC bottom part and the VV Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 44 of 117 atmosphere (an implicit junction), that not considers the choking effect in the divertor slits and calculates a flow rates between PC and VV higher than in the reality. The same little underestimation in the long term VV pressure, as for the PC, is also present. The suppression tank pressure trend (Figure B.16) is very similar to the experimental one excluding some strong oscillations at the beginning of the P2 experiment, confirming the non adequate geometrical characterisation of the ST vent system. In the medium and long term, on the contrary, these differences are minimised. The atmosphere temperature in the PC (Figure B.17) calculated by ECART follows correctly the experimental temperatures during the whole transient. The good code behaviour will be a constant also for the results on the PC atmosphere temperature in the next tests (apart the low injection rate tests P6 and P7). This good results is due to the strong wetting of the PC wall surfaces, partially simulated in the nodalisation submerging the wall into the sump, that masks the problem of a non correct prediction of the heat transfer coefficients by turbulent convection highlighted in the following. On the contrary, for the VV atmosphere temperature (Figure B.18), where it is again possible to observe the three temporal phases described for the test P1, this agreement in the long term is true considering the calculated saturation temperature, while a superheating of about 10 °C is predicted by the code for the VV atmosphere. This could be due to: a) a possible wetting (by drops or rivulets from the PC) of the thermocouple bulbs that, in this case, could be able to measure the saturated water temperature and not the real VV air temperature; b) underestimation of the heat transfer coefficient between VV atmosphere and walls, internally calculated by ECART not considering the strong turbulence induced inside the small VV volume (turbulent conditions typical for injection in small volumes require an evaluation of the velocity field, not possible with lumped parameter codes as ECART). Also this questionable code behaviour will be a constant for all the results on the VV atmosphere temperature in the next tests (apart the two tests P6 and P7, where the reduced injection flow-rate inside the PC leads to lower turbulence conditions) and the relative comment will be not repeated in the following of the report. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 45 of 117 For the walls’ temperatures in PC and VV (reported respectively Figure B.19 and Figure B.20) all the comments referred to the previous case P1 can be repeated for the corresponding figures, with no changes. For the VV wall temperatures (Figure B.20) the behaviour of the experimental signal TVW-15 is to be highlighted: it presents oscillations that can be explained with the presence of a random wetting of the surface due to a liquid water flow (drops or rivulets). For the drain tank pressure and atmospheric temperature (Figure B.21 and Figure B.22) is still valid what said for the case P1, in particular for the presence of the initial strong compression effect and the quite good agreement in the long term phase. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 46 of 117 5.3 ICE CASE P3 5.3.1 Main results The following Table 5.3 summarizes the comparison between the ECART post test calculations and the P3 experimental data. The main difference respect to the previous test P2 is the higher pressure inside the boiler (3 MPa vs. 2 MPa) and the vacuum vessel and divertor temperatures, lower in the case P3. P3 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 2 s 238.6 kPa 2s 2s 41 kPa 40 kPa 31.9 kPa 31.3 kPa ECART T = 2 s 223 kPa 2 s (imposed) 2 s (imposed) 35.5 kPa 36.5 kPa 26.3 kPa 34.1 kPa Table 5.3: P3 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.23 to Figure B.33, compared with the experimental trends and in Table B.1. 5.3.2 Analysis of the results Obviously, considering the small changes in the boundary conditions (practically only the boiler pressure), the results obtained in this case P3 are very similar to the ones of the previous tests P1 and P2. The PC pressure (Figure B.24 and Figure B.25) is on time respect the experimental pressure and also the value of the pressure peak is in good agreement with the experimental one. The long term PC behaviour shows again the little overestimation of the flow towards the ST. The VV total pressure (Figure B.26) is overestimated in the ECART simulation and the same little underestimation in the long term pressure, as for the PC, is also present. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 47 of 117 The ST pressure trend (Figure B.27) is very similar to the experimental one excluding the strong oscillations at the beginning of the experiment while, in the medium and long term, the differences are minimised. The atmosphere temperature in the PC (Figure B.28) follows correctly the experimental data during the whole transient. For the VV atmosphere temperature (Figure B.29) this agreement is true considering the calculated saturation temperature, while a superheating of about 10 °C is again predicted by the code. Also for the drain tank pressure and atmosphere temperature (Figure B.32 and Figure B.33) is still valid what said previously, in particular for the presence of the initial strong compression effect and the quite good long term agreement. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 48 of 117 5.4 ICE CASE P4 5.4.1 Main results The following Table 5.4 summarizes the comparison between the ECART post test calculations and the P4 experimental data. The main differences respect to the previous test P2 are the higher initial value of the pressure of the DT (4300 Pa vs. 3200 Pa) and the temperature of the water exiting the boiler (125 °C in P4 against 150 °C in P2). P4 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 2 s 221.8 kPa 2.5 s 2.5 s 31.1 kPa 29.9 kPa 27.5 kPa 21.6 kPa ECART t = 2.2 s 214.5 kPa 2.5 s (imposed) 2.5 s (imposed) 25.5 kPa 26.3 kPa 20.8 kPa; 24.2 kPa Table 5.4: P4 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.34 to Figure B.44, compared with the experimental trends and in Table B.1. 5.4.2 Analysis of the results Obviously, for the small differences in the boundary and initial conditions of the test, the ECART results obtained in this case P4 are qualitatively similar to the ones of the previous ICE tests P2 and P3. For the total pressure in the PC (Figure B.35 and Figure B.36) and the total pressure in VV (Figure B.37) what wrote previously is valid for this case too, in particular about the low underestimation in the long term phase of the test. The calculated pressure trend in the suppression tank (Figure B.38) shows again the initial oscillations and the long term agreement. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 49 of 117 Also on the temperatures in the PC (Figure B.39), in the VV (Figure B.40), in the PC walls (Figure B.41) and in the VV walls (Figure B.42) can be made comments similar to those made previously. Again, the evolution of the atmosphere temperature in the DT is well simulated in the long term (Figure B.44) but this does not occur for the pressure (Figure B.43). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 50 of 117 5.5 ICE CASE P5 5.5.1 Main results The following Table 5.5 summarizes the comparison between the ECART post test calculations and the P5 experimental data. This test, with a large water injection into the PC (three large nozzles) as in the previous four tests, has been performed reducing the number of the relief pipes (RP), linking the PC to the ST, from 3, as in the previous tests, to a single RP. It is necessary to recall that the opening time in the rupture disk are tuned in order to fit the simulated peak of the pressure with the experimental one. This is the cause of the difference between the open time of the suppression tank rupture disk, in this case. The effects deriving from this strong flow area reduction on the resulting thermal-hydraulic transient inside the ICE facility is widely described in [Takase, 2002]. In particular, in case of the three RPs, a lots of vapour is condensed within the ST and then the pressure in the PC decreases larger than the case where the RP is one. P5 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 8 s 271 kPa 2.5 s 4.0 s 33.4 kPa 31.9 kPa 35.2 kPa 20.2 kPa ECART T = 8 s 291 kPa 2.5 s (imposed) 8.0 s (imposed) 27.1 kPa 28.1 kPa 30.8 kPa 26.1 kPa Table 5.5: P5 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.45 to Figure B.55, compared with the experimental trends. 5.5.2 Analysis of the results The calculated ECART results are in good agreement with the experimental ones also in this test with a strong reduction of the mass flow-rate into the ST (Figure B.45). Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 51 of 117 The short term agreement for the PC pressure (Figure B.46) is again linked to the increase in the delay of the RD opening towards the ST, that compensate the low steam production in the interaction with the PC structures and the injected water while the long term behaviour for the pressure inside the PC (Figure B.47) and inside the VV (Figure B.48) is better predicted than in the previous cases. On the contrary, there is an agreement between the experimental pressure and the calculated results in the ST (Figure B.49) only during the initial flow discharge, also if the pressurisation rate is faster in the code prediction for the long term, after that ECART overestimates the final pressure increase in the ST. Again the nodalisation adopted for this tank and the available initial and boundary conditions are questionable. The atmosphere temperature in the PC (Figure B.50), in the VV (Figure B.51), in the PC walls (Figure B.52) and in the VV walls (Figure B.53) can be explained as in the previous cases, not depending on the pressurisation level reached by the facility. The higher experimental temperature supplied by the probe TVW-15 (Figure B.53), if compared with the temperature calculated for a wetted surface, points out the non occurrence of the water wetting in this particular case. The calculated pressure (Figure B.54) and temperature (Figure B.55) in the DT are in very good agreement with the experimental data, showing the effect of the reduced number of RPs, with a higher pressurisation level (practically doubled) reached inside the DT in comparison with the previous four ICE tests. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 52 of 117 5.6 ICE CASE P6 5.6.1 Main results The following Table 5.6 summarizes the comparison between the ECART post test calculations and the P6 experimental data. This test has been performed with a strong reduction of the mass flow rate injected into the PC (only a single small nozzle was been employed in the P6 test procedure) but increasing the injection time from 45 to 600 seconds. P6 Max p in the PC DT open time ST open time End (1200 s) PC VV DT ST Experimental t = 7.5 s 170.8 kPa 6s 8s 37.7 kPa 35.5 kPa 37.6 kPa 30.1 kPa ECART t = 7.5 s 170.8 kPa 6 s (imposed) 7.5 s (imposed) 46.6 kPa 46.6 kPa 37.6 kPa 41.8 kPa Table 5.6: P6 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.56 to Figure B.66, compared with the experimental trends and in Table B.1. 5.6.2 Analysis of the results The peak of pressure calculated by ECART in PC (Figure B.57 and Figure B.58) and in VV (Figure B.59) is in very good agreement with the experiment data. This is due again to the introduction of the delayed opening (about 2 s) of the DT and ST respect to the set points established (0.11 and 0.15 MPa respectively). In the short term pressurisation of the PC (Figure B.57 and Figure 5.1), a characteristic code result at about 4.5 s has to be highlighted. The quite evident change in the PC pressurisation rate is linked to the poor simulation of the interactions between the forming water sump and the hot PC structures, responsible for the steam production. In ECART, this interaction sump/structure is simulated starting only from a minimum water level for the sump; so, when the initial sump mass is null, the formation of the required minimum level leads to a time delay in the starting of the Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 53 of 117 interaction sump/structure. This delay is shown in the following Figure 5.1 where, at about 4.5 s, is relevant the strong increase in the values of the heat transfer coefficient utilised for the PC 2 wall (from about 20 to about 200 W/m K), that only from this time begins to exchange with the forming sump and not only with the PC atmosphere. 0.18 360 0.16 320 0.14 280 PC Pressure (MPa) 0.12 240 0.10 200 0.08 160 0.06 120 0.04 80 0.02 40 0.00 Heat transfer coefficient (W/m2K) ECART Exp 'HTC sump' 0 0 1 2 3 4 5 6 7 8 9 10 Time (s) Figure 5.1: ICE P6 – Heat transfer coefficient for the PC. Again the suppression tank calculated pressure (Figure B.60) is in quite good agreement only in the injection phase (600 s in this test P6). After this time, there is a decrease of the pressure inside the ST, not predicted by ECART, that contemporarily predicts also a relevant flow-rate entering into the ST (Figure B.56) after the injection stopping. This result further confirms the problems, just highlighted, in the ST characterisation. The decrease of the simulated temperature in the PC atmosphere (Figure B.61) is congruent with the experimental data, but the large increase after about 850 s is not predicted by the code and the superheating in the PC atmosphere is not evidenced by the calculations. Different is the Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 54 of 117 situation for the VV’s temperature (Figure B.62) where the atmosphere superheating of about 60 °C is correctly calculated by ECART. To be noted the good behaviour of ECART for this low turbulence test, with the presence of a minor overestimation of the energy shearing between atmosphere and walls. For the wall temperature trends in the PC (Figure B.63) the calculated values are higher than in the experiment, but with a similar trend only in the first part of the transient, where a complete wetting of the surfaces is the resulting behaviour. After the injection stopping, the final growing trend is not predicted by the code. Probably, the heat transfer phenomena are dominated by a low but still turbulent convection, not predicted by the natural convection models employed by ECART in this final part of the simulation. For the wall temperature trends in the VV (Figure B.64) the agreement is quite better, as in the previous calculations. The calculated pressure (Figure B.65) in the DT, excluding the compression effect at the beginning of the simulation, not present in the P6 experiment, are quite satisfactory. Instead, the DT temperature (Figure B.66) is largely overestimated in the initial phase while, in the long term, follows satisfactorily the experimental trend. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 55 of 117 5.7 ICE CASE P7 5.7.1 Main results The following Table 5.7 summarizes the comparison between the ECART post test calculations and the P7 experimental data. Also this test, as the previous P6, has been performed with a strong reduction of the mass flow-rate injected into the PC (a single small nozzle) and a longer injection time (600 s). The main difference is the decrease of the initial temperature of the VV zone, now about 120 °C against the about 210 °C of the previous test P6. P7 Max p in the PC DT open time ST open time End (1200 s) PC VV DT ST Experimental t = 13.5 s 156.3 kPa 8.5 s 8.5 s 19 kPa 17.3 kPa 19 kPa 11.2 kPa ECART t = 18.5 s 156.1 kPa 8.5 s (imposed) 8.5 s (imposed) 19 kPa 18.6 kPa 17.5 kPa 14 kPa Table 5.7: P7 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.67 to Figure B.77, compared with the experimental trends and in Table B.1. 5.7.2 Analysis of the results The timing of the peak of the calculated pressures in PC (Figure B.68 and Figure B.69) and in VV (Figure B.70) are strongly delayed (5 s) if compared with the results obtained in the other tests and also the time trend of the two curves maintain high values for a long time, if compared with the experimental data. On the contrary, the long term behaviour is quite satisfactory. The time delay in the pressurisation history of the facility is due to the lack of the pressurisation effect of the steam forming in the interactions with the VV structures, that in this test P7 are colder respect to the P6 conditions. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 56 of 117 The behaviour of the ST calculated pressure (Figure B.71) is very similar to the results obtained in the previous test P6, confirming the previous conclusions on a worst characterization of the tank geometry. The temperature in PC (Figure B.72) shows again the large superheating (more than 50 °C) highlighted previously, with the same problems about the ECART prediction of the energy shearing between atmosphere and walls. The lower wetting of the PC surface in these two tests P6 and P7 (both performed with only one small injection nozzle) is not sufficient to mask this problem as in the other ICE tests. Also for the atmosphere temperature in the VV (Figure B.73), the comments can be the same of the previous test P6, with the experimental evidence and the code prediction of an atmosphere superheating. This is true also for the PC and VV wall temperatures, respectively reported in Figure B.74 and in Figure B.75. Calculated pressure (Figure B.76) and atmospheric temperature (Figure B.77) in the DT approximate correctly the P7 experimental data, excluding again the initial compression effect predicted by ECART. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 57 of 117 5.8 ICE CASE P8 5.8.1 Main results The following Table 5.8 summarizes the comparison between the ECART post test calculations and the P8 experimental data. This is an intermediate test for the water flow-rate released into the PC, performed with three small nozzles with an injection time equal to 200 s. The other initial and boundary conditions are similar to the ones of the previous test P7. P8 Max p in the PC DT open time ST open time End (600 s) PC VV DT ST Experimental t = 6.5 s 170.2 kPa 4.5 s 7.5 s 22 kPa 20.7 kPa 21.1 kPa 9.4 kPa ECART t = 6.5 s 170.2 kPa 4 s (imposed) 6.5 s (imposed) 15.6 kPa 15.8 kPa 16.3 kPa 11.4 kPa Table 5.8: P8 – Experimental data vs. ECART results. The main ECART results are also shown from Figure B.78 to Figure B.88, compared with the experimental trends and in Table B.1. 5.8.2 Analysis of the results The simulated peak of pressure in PC (Figure B.79 and Figure B.80) and in VV (Figure B.81) are in very good agreement with the experimental data. This is true also for the pressure trend in the ST (Figure B.82) that is only slightly overestimated in its final value (11.4 kPa vs. 9.4 kPa). Satisfactory is also the behaviour of the atmosphere temperature of PC (Figure B.83) while, for the VV atmosphere (Figure B.84), a superheating of about 30 °C is predicted by ECART but this superheating is present in the experimental data only in a very short period, before 100 s. Note that the injection flow-rate is now higher than in the previous two tests, performed with only one Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 58 of 117 small nozzle, leading again to an high turbulence inside the VV atmosphere and to the problem in the energy shearing between atmosphere and wall predicted in the ECART calculations. The wall temperatures for the heat structures in PC and VV (respectively reported in Figure B.85 and Figure B.86) show the same behaviour of the previous test P7, as for the satisfactory trends of the DT calculated pressure (Figure B.87) and temperature (Figure B.88) not in the short term but in the long term. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 59 of 117 6. CONCLUSIONS FOR ICE TESTS P1 - P8 CALCULATIONS The post test calculations for the P1 – P8 ICE tests provided useful information on the capability of the ECART code in predicting thermal-hydraulics transients expected in the future fusion reactors. These activities have been carried out in the general framework of the ECART validation phase for its application to fusion reactor. All the real initial conditions derived from the ICE experimental data have been imposed in the 8 code input decks in order to start the test simulations in the more correct way, also if these real conditions have been sometimes different from the initial test specifications. During the input deck preparation, some problems have been also highlighted on the completeness of the ICE experimental data (as for the water level inside the ST linked to the information on the amount of the initial water mass). The obtained differences between the experimental and calculated results are quite satisfactory for the most important thermal-hydraulics parameters (as the peak of PC pressure, time of the peak, long term pressure behaviour and maximum temperatures) because they are lower than 20% for the most part of them (see the quantitative comparison in Table B.1). For the ICE pressure transients, the main problems have been highlighted in the prediction of the long term depressurization phase, after the end of the water injection into the PC. This is a temporal phase where the pressure trends are strongly influenced by the predicted mass flow from the PC to the ST. An unsatisfactory characterization of the ST vent geometry and doubtful tank initial conditions led to some discrepancies in the code pressure results. Summarizing, the agreement of the pressure calculated results with the experimental data are due essentially to: a) the adoption of the real initial conditions of the ICE P1 – P8 experiments; b) the forced use of heat transfer coefficients taking into account the presence of the water in the bottom part of the PC and VV volumes (through the tuning of the heat structure elevation), also for the partial simulation of the “jet impingement” phenomena against the PC walls. DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 60 of 117 These good results are especially true for the pressure and temperature transients inside the PC and for pressure inside the VV, while a questionable agreement has been obtained in the ECART calculations for: a) the “VV atmosphere temperatures”, where an overestimation of the energy shearing between atmosphere and walls is present especially for the high turbulence tests, due to the needs of the turbulent convection models implemented inside the code (these model are correctly implemented but being ECART a lumped parameter code, the velocity field necessary as input datum for these models can be only roughly estimated); b) the “PC and VV wall temperatures”, due to the strong presence in the ICE tests of local phenomena, as liquid drops or rivulets, impossible to be correctly simulated and for the energy shearing problem highlighted in the previous point a). However, the evaluation of the ICE wall temperatures performed by ECART can be considered adequate for the scope of this type of code assessment analysis. Concluding, the main problem highlighted is about the heat transfer models that in ECART are automatically calculated by the code, being the user not free to change the heat transfer regime. The code package gives quite satisfactory results if the heat transfer regime between atmosphere and wall is similar to a natural convection situation or condensation. But, during a “jet injection”, as inside the ICE PC, or “turbulent” situations also the regions outside of the target of the jet or inside the lower VV are subjected to a “turbulent” regime and the calculated values of the heat transfer coefficients by the ECART models are underestimated (the evaluation of the velocity field is only indicative and partial for a lumped parameter code). Some possible improvements are foreseen in the future for the internal modelling of the heat transfer coefficients, now more adequate in “stagnant” conditions than in “highly turbulent” situations, especially in small volumes as the ICE ones. These considerations are however of secondary importance for large volumes as in ITER. Other useful modifications of the ECART code could be: a) a more refined calculation of the surface area wetted by an increasing water pool inside a horizontal cylindrical vessel (at the moment ECART heat structures have only a vertical orientation respect to the control volume, so only the transient of the wetted surface of a vertical cylinder is correctly predicted). This improvement will allow a more accurate Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 61 of 117 simulation of the steam production for the interaction of the released water coolant with the hot structures present in the bottom part of a VV. b) Possibility to define implicit junctions having a time/pressure dependent area. In this way, besides the immediate benefit, could be also possible to investigate about the influence of the use of a “no chocked” model for the evaluation of the mass flow-rate on the thermal-hydraulics transient. c) Possibility to define “combined” trip signals (i.e. a pressure trip plus a time delay) and a flow area time history for the explicit junctions definition; this modification will allow a more accurate characterisation of valves or RD behaviour. d) Finally, for the practical solution of the problem on the turbulent heat transfer, the possibility to use time-dependent input dials for the values of heat transfer coefficients calculated by the code (now it is possible to use only a constant value). The modification could be useful for the simulation of heat transfer conditions dominated by a high turbulence, especially if an external evaluation of the velocity field, through a CFD code, could be available. This CFD evaluation of the velocity field could be necessary also for the quantitative evaluation of other phenomena relevant for the ITER safety analysis, as the dust resuspension inside the VV. DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 62 of 117 REFERENCES [Caruso, 2002] G. Caruso, M.T. Porfiri, “CONSEN Validation against ICE Experimental Campaign 2001”, ENEA ERG-FUS, SA-SE-R-60, December 2002 [Meloni, 2002] P. Meloni, M.T. Porfiri, “ISAS Calculation for Inlet of Coolant (ICE) Experiments in 2001: Pre and Post Test”, ENEA ERG-FUS, SA-SE-R-53, December 2002 [Oriolo, 1998] F. Oriolo, S. Paci, “DCMN Calculations for the ICE Facility”, Atti del Dipartimento di Costruzioni Meccaniche e Nucleari, Pisa, DCMN 016 (98). [Paci, 2000] S. Paci, “DIMNP Pre-Test Calculations for the EVITA Facility Using the ECART Code”, Atti del Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Pisa, DIMNP 017 (00). [Parozzi, 1997a] F. Parozzi et al., “ECART USER MANUAL Part 1: User’s Guidance”, ENEL Nuclear Energy Division Report, Milan, May 1997. [Parozzi, 1997b] F. Parozzi et al., “ECART USER MANUAL Part 2: Code Structure and Theory”, ENEL Nuclear Energy Division Report, Milan, May 1997. [Porfiri, 2002] M.T. Porfiri, ENEA FUS Frascati, private communication, e- mail October 15th, 2002. [Porfiri, 2003] M.T. Porfiri, ENEA FUS Frascati, private communication, e- mail April 11th, 2003. [Porfiri, 2004] M.T. Porfiri, ENEA FUS Frascati, private communication, e- mail January 26th, 2004. [Takase, 2001a] K. Takase, “Upgraded ICE specifications”, Adobe Acrobat© pdf electronic file, May 2001, JAERI, Japan [Takase, 2001b] K. Takase, H. Akimoto, L.N. Topilski, “Results of two-phase flow experiments with an integrated Ingress-of-Coolant Event (ICE) test facility for ITER safety”, Fusion Engineering and Design, Vol. 54 (2001), pp. 593 - 603. Associazione ENEA-EURATOM sulla Fusione [Takase, 2002] DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 63 of 117 K. Takase, Y. Ose, H. Akimoto, “Three-dimensional analysis of watervapor void fraction in a fusion experimental reactor under water ingress”, Fusion Engineering and Design, Vol. 63 (2002), pp. 429 - 436. [Topilski, 2003] L.N. Topilski, "Comparison of the results of the ICE post-test calculations for cases P1- P8", S 84 RI 20 03-05-16 R 0.1, May 3rd, 2003 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Appendix A: ECART Input deck for Test P1 $LIST DIMNP ICE Post test using ECART ICE sequence case 1 $======================================================================= $$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $$$ GENERAL DATA SECTION $$$ $$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $ $ IPROG 0 $ NREST NONCN NVOL NBE NJUN NSPIL NSTRUC NMAT NTABP 0 2 5 1 2 4 7 1 3 $$$ NON CONDENSABLE GAS COMPONENTS $ CHN CHN 'N2' 'O2' $======================================================================= $$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $$$ THERMAL-HYDRAULIC SECTION $$$ $$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$ $ $======================== VOLUME DATA =================================* $------------------------------------------------------------------$$ VOLUME 1 - Plasma Chamber $ CHVOL RHOUGHV PHVOL IAXIS 'PC' 1.E-4 1.885 0 $ AHOR ALNGTH PHIVOL IGEOM 0.283 2.1 0. 0 $ IOPT 1 $ PVOL TLVOL XLVOL TGVOL XGVOL ALGLEV 1.0e3 501.1 0. 501.1 1. 0. $ ANVOL (N2) ANVOL (O2) 0.7980 0.2000 $------------------------------------------------------------------$$ VOLUME 2 - VACUUM VESSEL $ CHVOL RHOUGHV PHVOL IAXIS 'VV' 1.E-4 1.571 0 $ AHOR ALNGTH PHIVOL IGEOM 0.196 1.571 0. 0 $ IOPT 1 $ PVOL TLVOL XLVOL TGVOL XGVOL ALGLEV 1.0e3 500.1 0. 500.1 1. 0. $ ANVOL (N2) ANVOL (O2) 0.7980 0.2000 $------------------------------------------------------------------$$ VOLUME 3 - SUPPRESSION TANK $ CHVOL RHOUGHV PHVOL IAXIS 'ST' 1.E-4 0.503 1 $ VNEXT FAREXT VNINT FARINT NVVOL 1. 1.0 0. 1.0 2 $ ZVOL AEXT BEXT AINT BINT 0. 0.503 1.0 0.0 0.0 1.9624 0.503 1.0 0.0 0.0 $ IOPT 1 $ PVOL TLVOL XLVOL TGVOL XGVOL ALGLEV 3.0e3 295.1 0. 295.1 1. 0.98 $ ANVOL (N2) ANVOL (O2) 0.7980 0.2000 $------------------------------------------------------------------$$ VOLUME 4 - DRAIN TANK $ CHVOL RHOUGHV PHVOL IAXIS 'DT' 1.E-4 1.916 0 $ AHOR ALNGTH PHIVOL IGEOM 0.273 1.6 0. 0 $ IOPT 1 $ PVOL TLVOL XLVOL TGVOL XGVOL ALGLEV 3.3e3 292.1 0. 292.1 1. 0.0 PAGE 64 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 $ ANVOL (N2) ANVOL (O2) 0.7980 0.2000 $------------------------------------------------------------------$$ VOLUME 5 - BOILER PIPE $ CHVOL RHOUGHV PHVOL IAXIS 'PBOIL' 1.E-4 0.166 0 $ AHOR ALNGTH PHIVOL IGEOM 0.002 2.75 0. 0 $ IOPT 1 $ PVOL TLVOL XLVOL TGVOL XGVOL ALGLEV 2.e6 423.15 0. 423.15 0. 0.0526 $ ANVOL (N2) 0.0 ANVOL (O2) 0.0 $------------------------------------------------------------------$$ BACK ENVIRONMENT 1 - BOILER $ CHBE NVBE CHCNBE TCONBE 'BOILER' 4 'DUMMY' 0. $ TBE PBET TLBET TGBET ALGBET ANBET1 ANBET2 0. 2.00e6 423.15 423.15 0. 0. 0. 7.5 1.57e6 423.15 423.15 0. 0. 0. 45.0 1.62e6 423.15 423.15 0. 0. 0. 600.0 1.62e6 423.15 423.15 0. 0. 0. $ $======================= IMPLICIT JUNCTION DATA =======================* $------------------------------------------------------------------$$ JUNCTION 1 - BOILER -> PIPE (PBOIL) $ CHJUN CHFRJ CHTOJ ZFRJUN ZTOJUN DZFRJU DZTOJU 'BOPIPE' 'BOILER' 'PBOIL' 0. 0.02 0. 0.02 $ THTFRJ PHIFRJ THTTOJ PHITOJ IHOMFJ IHOMTJ ISCRUB -90. 0. 0. 0. 0 0 0 $ AJUN DJUN AKFJUN AKRJUN WGJUN IRDJUN 2.0e-3 0.0505 1.0 1. 0.0 0 $------------------------------------------------------------------$$ JUNCTION 2 - PC -> VV $ CHJUN CHFRJ CHTOJ ZFRJUN ZTOJUN DZFRJU DZTOJU 'DIV' 'PC' 'VV' 0.0 0.45 0.01 0.0 $ THTFRJ PHIFRJ THTTOJ PHITOJ IHOMFJ IHOMTJ ISCRUB -90. 0. -90. 0. 1 1 0 $ AJUN DJUN AKFJUN AKRJUN WGJUN IRDJUN 0.0016 0.0451 0.5 0.5 0.0 0 $------------------------------------------------------------------$ $======================= EXPLICIT JUNCTION DATA =======================* $------------------------------------------------------------------$$ S&F 1 - INJECTION OF STEAM IN PC $ CHSPI ITYSPI CHFRSP CHTOSP ZFRSPI DZFRSP ZTOSPI 'INJECT' 4 'PBOIL' 'PC' 0.026 0.0 0.45 $ DZTOSP THTFRS PHIFRS THTTOS PHITOS IHOMFS IHOMTS 0.0 0. 0. 0. 0. 0 0 $ ISCRUB 0 $ ICRTSP TOPSPI TCLSPI POPSPI PCLSPI DZTLIN PREFSP -1 0.1 45. 10.e6 10.e6 0.0 0.0 $ CTOSP TAUSP 0.0 0.0 $ AREFF CDL CDV 1.3e-4 0.9 0.9 $------------------------------------------------------------------$$ S&F 2 - PC -> ST $ CHSPI ITYSPI CHFRSP CHTOSP ZFRSPI DZFRSP ZTOSPI 'RDST' 4 'PC' 'ST' 0.55 0. 0.85 $ DZTOSP THTFRS PHIFRS THTTOS PHITOS IHOMFS IHOMTS 0.0 0. 0. -90. 0. 0 0 $ ISCRUB 0 $ ICRTSP TOPSPI TCLSPI POPSPI PCLSPI DZTLIN PREFSP -1 2.5 99999. 1.50e6 0.0 2.0 0.0 $ CTOSP TAUSP 0.0 0.0 $ AREFF CDL CDV 0.003 0.6 0.6 PAGE 65 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 $------------------------------------------------------------------$$ S&F 3 - VV -> DT $ CHSPI ITYSPI CHFRSP CHTOSP ZFRSPI DZFRSP ZTOSPI 'RDDT' 4 'VV' 'DT' 0.0 0.00 0.5 $ DZTOSP THTFRS PHIFRS THTTOS PHITOS IHOMFS IHOMTS 0.0 -90. 0. -90. 0. 1 0 $ ISCRUB 0 $ ICRTSP TOPSPI TCLSPI POPSPI PCLSPI DZTLIN PREFSP -1 2.5 99999. 1.10e6 0.0 1.0 0.0 $ CTOSP TAUSP 0.0 0.0 $ AREFF CDL CDV 1.e-5 0.7 0.7 $------------------------------------------------------------------$$ S&F 4 - PC -> DT $ CHSPI ITYSPI CHFRSP CHTOSP ZFRSPI DZFRSP ZTOSPI 'RDDT2' 4 'PC' 'DT' 0.0 0.00 0.5 $ DZTOSP THTFRS PHIFRS THTTOS PHITOS IHOMFS IHOMTS 0.0 -90. 0. -90. 0. 1 0 $ ISCRUB 0 $ ICRTSP TOPSPI TCLSPI POPSPI PCLSPI DZTLIN PREFSP -1 2.5 99999. 1.10e6 0.0 1.5 0.0 $ CTOSP TAUSP 0.0 0.0 $ AREFF CDL CDV 5.e-5 0.7 0.7 $======================= STRUCTURE DATA ===============================* $ $------------------------------------------------------------------$$ STRUCTURE 1 - PC WALLS $ CHSTRU ITIPO RI NREG AREAI AREAE CHVINT 'PCWALL' 2 0.6 1 3.313 3.4 'PC' $ CHVEXT DHI DHE HFOULI HFOULE FACWI FACWE '&ENVIR' 0.6 0.6 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0. 0.0 0. 0.6 $ NVENV 2 $ TENV TMENVT HENVT 0. 500.15 0. 600. 500.15 0. $ DREG NINREG FQREG ITPREG IMREG 0.01 5 0. 1 1 $------------------------------------------------------------------$$ STRUCTURE 2 - VV WALLS $ CHSTRU ITIPO RI NREG AREAI AREAE CHVINT 'VVWALL' 2 0.5 1 2.71 2.8 'VV' $ CHVEXT DHI DHE HFOULI HFOULE FACWI FACWE '&ENVIR' 0.5 0.5 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0. 0.5 0. 0.5 $ NVENV 2 $ TENV TMENVT HENVT 0. 500.15 0. 600. 500.15 0. $ DREG NINREG FQREG ITPREG IMREG 0.01 5 0. 2 1 $------------------------------------------------------------------$$ STRUCTURE 3 - ST WALLS $ CHSTRU ITIPO RI NREG AREAI AREAE CHVINT 'STWALL' 2 0.4 1 4.926 5.0492 'ST' $ CHVEXT DHI DHE HFOULI HFOULE FACWI FACWE '&ENVIR' 0.8 0.8 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0. 1.96 0. 1.96 $ NVENV 2 $ TENV TMENVT HENVT 0. 293.15 10. 600. 293.15 10. $ DREG NINREG FQREG ITPREG IMREG PAGE 66 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 0.01 5 0. 0 1 $------------------------------------------------------------------$$ STRUCTURE 4 - DT WALLS $ CHSTRU ITIPO RI NREG AREAI AREAE CHVINT 'DTWALL' 2 0.4 1 2.96 3.0 'DT' $ CHVEXT DHI DHE HFOULI HFOULE FACWI FACWE '&ENVIR' 0.6 0.6 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0. 0.59 0. 0.59 $ NVENV 2 $ TENV TMENVT HENVT 0. 293.15 10. 600. 293.15 10. $ DREG NINREG FQREG ITPREG IMREG 0.01 5 0. 0 1 $------------------------------------------------------------------$$ STRUCTURE 5 - PC FLANGES $ CHSTRU 'FLNPC' $ ITIPO RI NREG AREAI AREAE CHVINT CHVEXT 1 0.0 1 0.5654 0.5654 'PC' '&ENVIR' $ DHI DHE HFOULI HFOULE FACWI FACWE 0.6 0.6 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0.0 0.6 0.0 0.6 $ NVENV 2 $ TENV TMENVT HENVT 0. 500.15 0. 600. 500.15 0. $ DREG NINREG FQREG ITPREG IMREG 0.06 12 0. 0 1 $------------------------------------------------------------------$$ STRUCTURE 6 - VV FLANGES $ CHSTRU 'FLNVV' $ ITIPO RI NREG AREAI AREAE CHVINT CHVEXT 1 0.0 1 0.3928 0.3928 'VV' '&ENVIR' $ DHI DHE HFOULI HFOULE FACWI FACWE 0.5 0.5 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0.0 0.5 0.0 0.5 $ NVENV 2 $ TENV TMENVT HENVT 0. 500.15 0. 600. 500.15 0. $ DREG NINREG FQREG ITPREG IMREG 0.06 12 0. 0 1 $------------------------------------------------------------------$$ STRUCTURE 7 - DIVERTOR $ CHSTRU 'DV' $ ITIPO RI NREG AREAI AREAE CHVINT CHVEXT 1 0.0 1 0.662 0.662 'PC' 'VV' $ DHI DHE HFOULI HFOULE FACWI FACWE 0.5 0.5 1.E10 1.E10 1. 1. $ ZBOTI ZTOPI ZBOTE ZTOPE 0.0 0.0 0.5 0.5 $ DREG NINREG FQREG ITPREG IMREG 0.012 6 0. 3 1 $ $======================= MATERIAL DATA ===============================* $------------------------------------------------------------------$$ MATERIAL 1 - STAINLESS STEEL $ $ THERMAL CONDUCTIVITY TABLE $ NAK 2 $ AKT AKV 0. 11.7 10000. 11.7 $ PAGE 67 of 117 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 $ HEAT CAPACITY TABLE $ NVHC 2 $ VHCT VHCV 0. 3.740E6 10000. 3.740E6 $ $====================== POWER DATA ================================== $------------------------------------------------------------------$$ HEATING IN STRUCTURE PC $ NPOW FPOW 3 0.03313 $ TPOW POWT 0. 45280.0 60. 422600.0 600. 422600.0 $------------------------------------------------------------------$$ HEATING IN STRUCTURE VV $ NPOW FPOW 3 0.027 $ TPOW POWT 0. 18450. 100. 332100.0 600. 332100.0 $------------------------------------------------------------------$$ HEATING IN STRUCTURE DV $ NPOW FPOW 4 0.007944 $ TPOW POWT 0. 0. 100. 377600.0 400. 692300.0 600. 692300.0 $ $======================= PUMP DATA ================================== $ NPUMP 0 $ $================ TIME ADVANCEMENT CONTROL DATA ======================* $ $ TEND NFREQ NPLTH 600. 4 22 $ TSTEA DTSTEA DTSTOU NJUDEL NSPDEL ICOUST -1. 0.01 0.5 0 0 1 $ TFREQ DTUP DTLW DTTROU DTTRPL ICOURT 10. 0.01 1.e-6 0.5 0.1 1 45. 0.01 1.e-6 0.5 0.5 1 100. 0.01 1.e-6 5. 0.5 1 600. 0.01 1.e-6 10. 5.0 1 $ CHPLOT CHPLO1 INDPL2 CONVFP NWCHPL 'PVOL' 'PC' 0 1.e-6 'PC press' 'PVOL' 'VV' 0 1.e-6 'VV press' 'PVOL' 'ST' 0 1.e-6 'ST press' 'PVOL' 'DT' 0 1.e-6 'DT press' 'TGVOL' 'PC' 0 0 'PC T' 'TGVOL' 'VV' 0 0 'VV T' 'TGVOL' 'ST' 0 0 'ST T' 'TGVOL' 'DT' 0 0 'DT T' 'WGSPIL' 'INJECT' 0 0 'inject' 'WGSPIL' 'RDST' 0 0 'w to ST' 'TSAT' 'PC' 0 0 'PC Tsat' 'TSAT' 'VV' 0 0 'VV Tsat' 'TSAT' 'ST' 0 0 'ST Tsat' 'TSAT' 'DT' 0 0 'DT Tsat' 'T' 'PCWALL' 1 0 'PC wall' 'T' 'VVWALL' 1 0 'VV wall' 'T' 'STWALL' 1 0 'ST wall' 'T' 'DTWALL' 1 0 'DT wall' 'T' 'FLNPC' 1 0 'PC flange' 'T' 'FLNVV' 1 0 'VV flange' 'T' 'DV' 1 0 'DV side PC' 'T' 'DV' 7 0 'DV side VV' 'AMVOL' 'TANK' 0 0 'gas mass Tank' $EOD PAGE 68 of 117 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione PAGE 69 of 117 Appendix B: Output Comparison Tables and Plots Time P max PC (s) P max PC (kPa) Time P max VV (s) P max VV (kPa) P max ST (kPa) P max DT (kPa) T max PC at. (°C) T min PC at. (°C) T max VV at. (°C) T min VV at. (°C) Tsat max VV at. (°C) Tsat min VV at. (°C) T max PC wall (°C) T min PC wall (°C) T max VV wall (°C) T min VV wall (°C) Time P max PC (s) P max PC (kPa) Time P max VV (s) P max VV (kPa) P max ST (kPa) P max DT (kPa) T max PC at. (°C) T min PC at. (°C) T max VV at. (°C) T min VV at. (°C) Tsat max VV at. (°C) Tsat min VV at. (°C) T max PC wall (°C) T min PC wall (°C) T max VV wall (°C) T min VV wall (°C) exp 2 372 2 368 48 37 227 112 226 79 226 79 228 79 229 81 P1 ECART diff % 2.5 0.5 s 371 0 2.5 0.5 s 363 -1 36 -25 28 -24 228 ns 127 13 310 37 151 91 141 -38 73 -8 228 ns 74 -5 228 ns 74 -9 exp 8 271 11 253 21 35 212 70 125 71 125 71 226 70 130 71 P5 ECART diff % 8 0. s 291 7 8.5 -2.5 s 288 14 26 24 31 -11 212 ns 69 -1 287 130 87 23 124 -1 68 -4 210 ns 68 -3 146 ns 69 -3 exp 2 271 2.5 227 31 32 211 73 125 74 125 74 227 74 131 75 P2 ECART diff % 2 0s 288 6 2.2 -0.3 s 270 19 33 6 27 -16 210 ns 71 -3 289 131 71 -4 130 4 71 -4 210 ns 72 -3 148 ns 72 -4 exp 7.5 171 7.5 168 34 43 226 76 210 90 210 90 231 75 212 77 P6 ECART diff % 7.5 0. s 171 0 7.5 0. s 171 2 42 24 38 -12 226 ns 80 5 268 28 137 52 115 -45 79 -12 227 ns 79 5 214 ns 80 4 exp 3 238 3 192 31 32 211 73 120 75 120 75 228 74 131 76 P3 ECART diff % 3 0s 223 -6 2.2 -0.3 s 214 11 34 10 27 -16 210 ns 72 -1 277 131 93 24 122 2 72 -4 212 ns 73 -1 150 ns 73 -4 exp 2 222 2.5 168 22 27 208 67 116 70 116 70 229 68 122 70 P4 ECART diff % 2.2 0.2 s 220 -1 2.4 -0.1 s 196 17 24 9 21 -21 208 ns 64 -4 280 141 83 19 120 3 64 -9 257 ns 64 -6 138 ns 65 -7 exp 14 156 14 153 11 21 215 58 134 61 134 61 230 57 134 64 P7 ECART diff % 18 4. s 156 0 18 4. s 156 2 14 27 23 10 212 ns 60 3 230 72 97 59 113 -16 58 -5 215 ns 58 2 148 ns 58 -9 exp 6.5 170 6.5 167 9.4 21 210 60 125 61 125 61 228 60 136 62 P8 ECART diff % 6.5 0. s 170 0 6.5 0. s 165 -1 11.4 21 21 0 210 ns 60 0 214 71 83 36 116 -7 55 -10 210 ns 57 -5 152 ns 58 -5 Table B.1: Summary of the main results for the cases P1 – P8. (* ns = not significant , blue= good agreement, green=satisfactory agreement, red= bad agreement) Associazione ENEA-EURATOM sulla Fusione B.1 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 70 of 117 Test P1 7 1.4 6 1.2 ECART Exp ECART w to ST 5 1.0 4 0.8 3 0.6 2 0.4 1 0.2 0 0 50 100 150 200 Flow rate to ST (kg/s) 0.0 300 250 Time (s) Figure B.1 ICE P1 – Flow rates. 0.40 0.35 0.30 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.25 ECART Exp 0.20 0.15 0.10 0.05 0.00 0 1 2 3 4 5 6 7 Time (s) Figure B.0.2 ICE P1 – PC Pressure (short term). 8 9 10 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 71 of 117 0.40 0.35 PC Pressure (MPa) 0.30 ECART Exp 0.25 0.20 0.15 0.10 0.05 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.3 ICE P1 – PC Pressure. 0.40 0.35 VV Pressure (MPa) 0.30 0.25 ECART Exp 0.20 0.15 0.10 0.05 0.00 0 100 200 300 400 Time (s) Figure B.4 ICE P1 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 72 of 117 0.06 0.05 ST Pressure (MPa) 0.04 0.03 ECART Exp 0.02 0.01 0.00 0 100 200 300 400 500 600 Time (s) Figure B.5 ICE P1 – ST Pressure. 503 230 483 210 ECART Exp 190 443 170 423 150 403 130 383 110 363 90 343 70 323 0 100 200 300 400 Time (s) Figure B.6 ICE P1 – PC Atmosphere Temperature. 500 50 600 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 73 of 117 330 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280 230 453 180 403 130 353 80 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30 600 Time (s) Figure B.7 ICE P1 – VV Atmosphere Temperature. 503 230 483 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 190 443 170 423 150 403 130 383 110 363 90 343 70 323 0 100 200 300 400 Time (s) Figure B.8 ICE P1 – PC Wall Temperature. 500 50 600 Temperature (°C) PC Wall Temperature (K) 463 210 EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 74 of 117 503 230 483 210 463 190 443 170 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 423 403 150 130 383 110 363 90 343 70 323 0 100 200 300 400 500 50 600 Time (s) Figure B.9 ICE P1 – VV Wall Temperature. 0.04 0.04 DT Pressure (MPa) 0.03 0.03 0.02 ECART Exp 0.02 0.01 0.01 0.00 0 100 200 300 400 Time (s) Figure B.10 ICE P1 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 75 of 117 363 90 353 80 343 70 333 60 ECART Exp 323 50 313 40 303 30 293 20 283 0 100 200 300 400 Time (s) Figure B.11 ICE P1 – DT Atmosphere Temperature. 500 10 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.2 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 76 of 117 Test P2 7 1.4 6 1.2 ECART Exp ECART w to ST 5 1.0 4 0.8 3 0.6 2 0.4 1 0.2 0 0 50 100 150 200 Flow rate to ST (kg/s) 0.0 300 250 Time (s) Figure B.12 ICE P2 – Flow rates. 0.35 0.30 0.25 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.20 ECART Exp 0.15 0.10 0.05 0.00 0 1 2 3 4 5 6 7 Time (s) Figure B.13 ICE P2 – PC Pressure (short term). 8 9 10 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 77 of 117 0.35 0.30 PC Pressure (MPa) 0.25 ECART Exp 0.20 0.15 0.10 0.05 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.14 ICE P2 – PC Pressure. 0.30 0.25 VV Pressure (MPa) 0.20 ECART Exp 0.15 0.10 0.05 0.00 0 100 200 300 400 Time (s) Figure B.15 ICE P2 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 78 of 117 0.08 0.07 ST Pressure (MPa) 0.06 0.05 0.04 ECART Exp 0.03 0.02 0.01 0.00 0 100 200 300 400 500 600 Time (s) Figure B.16 ICE P2 – ST Pressure. 503 230.0 483 210.0 ECART Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.17 ICE P2 – PC Atmosphere Temperature. 500 50.0 600 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 79 of 117 330.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280.0 230.0 453 180.0 403 130.0 353 80.0 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 600 Time (s) Figure B.18 ICE P2 – VV Atmosphere Temperature. 503 230.0 483 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.19 ICE P2 – PC Wall Temperature. 500 50.0 600 Temperature (°C) PC Wall Temperature (K) 463 210.0 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 503 80 of 117 230.0 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 483 463 210.0 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 500 50.0 600 Time (s) Figure B.20 ICE P2 – VV Wall Temperature. 0.04 0.03 DT Pressure (MPa) 0.03 0.02 ECART Exp 0.02 0.01 0.01 0.00 0 100 200 300 400 Time (s) Figure B.21 ICE P2 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) PAGE EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 81 of 117 363 90.0 353 80.0 343 70.0 333 60.0 ECART Exp 323 50.0 313 40.0 303 30.0 293 20.0 283 0 100 200 300 400 Time (s) Figure B.22 ICE P2 – DT Atmosphere Temperature. 500 10.0 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.3 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 82 of 117 Test P3 9 0.9 8 0.8 7 0.7 ECART Exp ECART w to ST 6 0.6 5 0.5 4 0.4 3 0.3 2 0.2 1 0.1 0 0 50 100 150 200 Flow rate to ST (kg/s) 0.0 300 250 Time (s) Figure B.23 ICE P3 – Flow rates. 0.30 0.25 0.20 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE ECART Exp 0.15 0.10 0.05 0.00 0 1 2 3 4 5 6 7 Time (s) Figure B.24 ICE P3 – PC Pressure (short term) 8 9 10 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 83 of 117 0.30 0.25 PC Pressure (MPa) 0.20 ECART Exp 0.15 0.10 0.05 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.25 ICE P3 – PC Pressure. 0.25 VV Pressure (MPa) 0.20 0.15 ECART Exp 0.10 0.05 0.00 0 100 200 300 400 Time (s) Figure B.26 ICE P3 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 84 of 117 0.040 0.035 ST Pressure (MPa) 0.030 0.025 0.020 ECART Exp 0.015 0.010 0.005 0.000 0 100 200 300 400 500 600 Time (s) Figure B.27 ICE P3 – ST Pressure. 503 230.0 483 210.0 ECART Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.28 ICE P3 – PC Atmosphere Temperature. 500 50.0 600 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 85 of 117 330.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280.0 230.0 453 180.0 403 130.0 353 80.0 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 600 Time (s) Figure B.29 ICE P3 – VV Atmosphere Temperature. 503 230.0 483 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.30 ICE P3 – PC Wall Temperature. 500 50.0 600 Temperature (°C) PC Wall Temperature (K) 463 210.0 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 503 86 of 117 230.0 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 483 463 210.0 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 500 50.0 600 Time (s) Figure B.31 ICE P3 – VV Wall Temperature. 0.035 0.030 DT Pressure (MPa) 0.025 0.020 ECART Exp 0.015 0.010 0.005 0.000 0 100 200 300 400 Time (s) Figure B.32 ICE P3 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) PAGE EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 87 of 117 363 90.0 353 80.0 343 70.0 333 60.0 ECART Exp 323 50.0 313 40.0 303 30.0 293 20.0 283 0 100 200 300 400 Time (s) Figure B.33 ICE P3 – DT Atmosphere Temperature. 500 10.0 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.1 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 88 of 117 Test P4 8 0.8 7 0.7 ECART Exp ECART w to ST 6 0.6 5 0.5 4 0.4 3 0.3 2 0.2 1 0.1 0 0 50 100 150 200 Flow rate to ST (kg/s) 0.0 300 250 Time (s) Figure B.34 ICE P4 – Flow rates. 0.25 0.20 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.15 ECART Exp 0.10 0.05 0.00 0 1 2 3 4 5 6 7 Time (s) Figure B.35 ICE P4 – PC Pressure (short term). 8 9 10 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 89 of 117 0.25 PC Pressure (MPa) 0.20 ECART Exp 0.15 0.10 0.05 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.36 ICE P4 – PC Pressure. 0.25 VV Pressure (MPa) 0.20 0.15 ECART Exp 0.10 0.05 0.00 0 100 200 300 400 Time (s) Figure B.37 ICE P4 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 90 of 117 0.030 0.025 ST Pressure (MPa) 0.020 0.015 ECART Exp 0.010 0.005 0.000 0 100 200 300 400 500 600 Time (s) Figure B.38 ICE P4 – ST Pressure. 503 230.0 483 210.0 ECART Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.39 ICE P4 – PC Atmosphere Temperature. 500 50.0 600 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 91 of 117 330.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280.0 230.0 453 180.0 403 130.0 353 80.0 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 600 Time (s) Figure B.40 ICE P4 – VV Atmosphere Temperature. 503 230.0 483 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.41 ICE P4 – PC Wall Temperature. 500 50.0 600 Temperature (°C) PC Wall Temperature (K) 463 210.0 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 503 92 of 117 230.0 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 483 463 210.0 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 500 50.0 600 Time (s) Figure B.42 ICE P4 – VV Wall Temperature. 0.030 0.025 DT Pressure (MPa) 0.020 0.015 ECART Exp 0.010 0.005 0.000 0 100 200 300 400 Time (s) Figure B.43 ICE P4 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) PAGE EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 93 of 117 363 90.0 353 80.0 343 70.0 333 60.0 ECART Exp 323 50.0 313 40.0 303 30.0 293 20.0 283 0 100 200 300 400 Time (s) Figure B.44 ICE P4 – DT Atmosphere Temperature. 500 10.0 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.1 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 94 of 117 Test P5 7 0.7 6 0.6 ECART Exp ECART w to ST 5 0.5 4 0.4 3 0.3 2 0.2 1 0.1 0 0 50 100 150 200 Flow rate to ST (kg/s) 0.0 300 250 Time (s) Figure B.45 ICE P5 – Flow rates. 0.35 0.30 0.25 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.20 ECART Exp 0.15 0.10 0.05 0.00 0 2 4 6 8 10 12 14 Time (s) Figure B.46 ICE P5 – PC Pressure (short term). 16 18 20 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 95 of 117 0.35 0.30 PC Pressure (MPa) 0.25 ECART Exp 0.20 0.15 0.10 0.05 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.47 ICE P5 – PC Pressure. 0.35 0.30 VV Pressure (MPa) 0.25 ECART Exp 0.20 0.15 0.10 0.05 0.00 0 100 200 300 400 Time (s) Figure B.48 ICE P5 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 96 of 117 0.030 0.025 ST Pressure (MPa) 0.020 0.015 ECART Exp 0.010 0.005 0.000 0 100 200 300 400 500 600 Time (s) Figure B.49 ICE P5 – ST Pressure. 503 230.0 483 210.0 ECART Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.50 ICE P5 – PC Atmosphere Temperature. 500 50.0 600 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 97 of 117 330.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280.0 230.0 453 180.0 403 130.0 353 80.0 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 600 Time (s) Figure B.51 ICE P5 – VV Atmosphere Temperature. 503 230.0 483 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 Time (s) Figure B.52 ICE P5 – PC Wall Temperature. 500 50.0 600 Temperature (°C) PC Wall Temperature (K) 463 210.0 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 503 98 of 117 230.0 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 483 463 210.0 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 100 200 300 400 500 50.0 600 Time (s) Figure B.53 ICE P5 – VV Wall Temperature. 0.050 0.045 0.040 DT Pressure (MPa) 0.035 0.030 0.025 ECART Exp 0.020 0.015 0.010 0.005 0.000 0 100 200 300 400 Time (s) Figure B.54 ICE P5 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) PAGE EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 99 of 117 363 90.0 353 80.0 343 70.0 333 60.0 ECART Exp 323 50.0 313 40.0 303 30.0 293 20.0 283 0 100 200 300 400 Time (s) Figure B.55 ICE P5 – DT Atmosphere Temperature. 500 10.0 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.1 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 100 of 117 Test P6 0.20 0.20 0.18 0.18 0.16 0.16 ECART Exp ECART w to ST 0.14 0.14 0.12 0.12 0.10 0.10 0.08 0.08 0.06 0.06 0.04 0.04 0.02 0.02 0.00 0 200 400 600 800 Flow rate to ST (kg/s) 0.00 1200 1000 Time (s) Figure B.56 ICE P6 – Flow rates. 0.20 0.18 0.16 0.14 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 2 4 6 8 10 12 14 Time (s) Figure B.57 ICE P6 – PC Pressure (short term). 16 18 20 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 101 of 117 0.20 0.18 0.16 PC Pressure (MPa) 0.14 ECART Exp 0.12 0.10 0.08 0.06 0.04 0.02 0.00 0 200 400 600 800 1000 1200 1000 1200 Time (s) Figure B.58 ICE P6 – PC Pressure. 0.20 0.18 0.16 VV Pressure (MPa) 0.14 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 200 400 600 800 Time (s) Figure B.59 ICE P6 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 102 of 117 0.045 0.040 0.035 ST Pressure (MPa) 0.030 0.025 ECART Exp 0.020 0.015 0.010 0.005 0.000 0 200 400 600 800 1000 1200 Time (s) Figure B.60 ICE P6 – ST Pressure. 503 230.0 483 210.0 ECART ECART T sat Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 200 400 600 800 Time (s) Figure B.61 ICE P6 – PC Atmosphere Temperature. 1000 50.0 1200 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 603 103 of 117 330.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 553 503 280.0 230.0 453 180.0 403 130.0 353 80.0 303 0 200 400 600 800 1000 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 1200 Time (s) Figure B.62 ICE P6 – VV Atmosphere Temperature. 523 250.0 503 230.0 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 483 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 200 400 600 800 Time (s) Figure B.63 ICE P6 – PC Wall Temperature. 1000 50.0 1200 Temperature (°C) PC Wall Temperature (K) 463 210.0 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 104 of 117 503 230 483 210 463 190 443 170 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 423 150 403 130 383 110 363 90 343 70 323 0 200 400 600 800 1000 50 1200 Time (s) Figure B.64 ICE P6 – VV Wall Temperature. 0.050 0.045 0.040 DT Pressure (MPa) 0.035 0.030 0.025 ECART Exp 0.020 0.015 0.010 0.005 0.000 0 200 400 600 800 Time (s) Figure B.65 ICE P6 – DT Pressure. 1000 1200 Temperature (°C) VV Wall Temperature (K) PAGE EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 105 of 117 463 190 443 170 423 150 403 130 383 ECART Exp 110 363 90 343 70 323 50 303 30 283 0 200 400 600 800 Time (s) Figure B.66 ICE P6 – DT Atmosphere Temperature. 1000 10 1200 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 Associazione ENEA-EURATOM sulla Fusione B.1 106 of 117 Test P7 0.18 0.18 0.16 0.16 0.14 0.14 ECART Exp ECART w to ST 0.12 0.12 0.10 0.10 0.08 0.08 0.06 0.06 0.04 0.04 0.02 0.02 0.00 0 200 400 600 800 Flow rate to ST (kg/s) 0.00 1200 1000 Time (s) Figure B.67 ICE P7 – Flow rates. 0.18 0.16 0.14 0.12 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.10 ECART Exp 0.08 0.06 0.04 0.02 0.00 0 5 10 15 20 25 30 Time (s) Figure B.68 ICE P7 – PC Pressure (short term). 35 40 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 107 of 117 0.18 0.16 0.14 PC Pressure (MPa) 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 200 400 600 800 1000 1200 1000 1200 Time (s) Figure B.69 ICE P7 – PC Pressure. 0.18 0.16 0.14 VV Pressure (MPa) 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 200 400 600 800 Time (s) Figure B.70 ICE P7 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 108 of 117 0.016 0.014 ST Pressure (MPa) 0.012 0.010 0.008 ECART Exp 0.006 0.004 0.002 0.000 0 200 400 600 800 1000 1200 Time (s) Figure B.71 ICE P7 – ST Pressure. 503 230.0 483 210.0 ECART ECART T sat Exp 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 200 400 600 800 Time (s) Figure B.72 ICE P7 – PC Atmosphere Temperature. 1000 50.0 1200 Temperature (°C) PC Atmosphere Temperature (K) 463 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 553 109 of 117 280.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 503 230.0 453 180.0 403 130.0 353 80.0 303 0 200 400 600 800 1000 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 1200 Time (s) Figure B.73 ICE P7 – VV Atmosphere Temperature. 503 230.0 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 483 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 0 200 400 600 800 Time (s) Figure B.74 ICE P7 – PC Wall Temperature. 1000 50.0 1200 Temperature (°C) PC Wall Temperature (K) 463 210.0 EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 110 of 117 433 160 413 140 393 120 373 100 353 80 333 60 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 313 40 293 0 200 400 600 800 1000 20 1200 Time (s) Figure B.75 ICE P7 – VV Wall Temperature. 0.025 DT Pressure (MPa) 0.020 0.015 ECART Exp 0.010 0.005 0.000 0 200 400 600 800 Time (s) Figure B.76 ICE P7 – DT Pressure. 1000 1200 Temperature (°C) VV Wall Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 111 of 117 423 150 403 130 383 110 363 90 ECART Exp 343 70 323 50 303 30 283 0 200 400 600 800 Time (s) Figure B.77 ICE P7 – DT Atmosphere Temperature. 1000 10 1200 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT Associazione ENEA-EURATOM sulla Fusione B.1 DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 112 of 117 Test P8 0.60 0.60 0.50 0.50 ECART Exp ECART w to ST 0.40 0.40 0.30 0.30 0.20 0.20 0.10 0.10 0.00 0 100 200 300 400 Flow rate to ST (kg/s) 0.00 600 500 Time (s) Figure B.78 ICE P8 – Flow rates. 0.18 0.16 ECART Exp 0.14 0.12 PC Pressure (MPa) Flow rate to PC (kg/s) PAGE 0.10 0.08 0.06 0.04 0.02 0.00 0 10 20 30 40 Time (s) Figure B.79 ICE P8 – PC Pressure (short term). 50 60 Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 113 of 117 0.18 0.16 0.14 PC Pressure (MPa) 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 100 200 300 400 500 600 500 600 Time (s) Figure B.80 ICE P8 – PC Pressure. 0.18 0.16 0.14 VV Pressure (MPa) 0.12 ECART Exp 0.10 0.08 0.06 0.04 0.02 0.00 0 100 200 300 400 Time (s) Figure B.81 ICE P8 – VV Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 114 of 117 0.014 0.012 ST Pressure (MPa) 0.010 0.008 ECART Exp 0.006 0.004 0.002 0.000 0 100 200 300 400 500 600 Time (s) 503 230.0 483 210.0 463 190.0 ECART ECART T sat PC atmosphere 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 50.0 303 0 100 200 300 400 Time (s) Figure B.83 ICE P8 – PC Atmosphere Temperature. 500 30.0 600 Temperature (°C) PC Atmosphere Temperature (K) Figure B.82 ICE P8 – ST Pressure. Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 553 115 of 117 280.0 ECART ECART T sat Exp Exp Exp Exp Exp Exp 503 453 230.0 180.0 403 130.0 353 80.0 303 0 100 200 300 400 500 Temperature (°C) VV Atmosphere Temperature (K) PAGE 30.0 600 Time (s) Figure B.84 ICE P8 – VV Atmosphere Temperature. 523 250.0 503 483 463 210.0 190.0 443 170.0 423 150.0 403 130.0 383 110.0 363 90.0 343 70.0 323 50.0 303 0 100 200 300 400 Time (s) Figure B.85 ICE P8 – PC Wall Temperature. 500 30.0 600 Temperature (°C) PC Wall Temperature (K) 230.0 'PC wall' 'DV side PC' TPW-7 TPW-26 TPW-18 EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 116 of 117 433 160.0 413 140.0 393 120.0 373 100.0 353 80.0 'VV wall' 'DV side VV' TVW-8 TVW-15 TVW-4 333 60.0 313 0 100 200 300 400 500 40.0 600 Time (s) Figure B.86 ICE P8 – VV Wall Temperature. 0.025 DT Pressure (MPa) 0.020 0.015 ECART Exp 0.010 0.005 0.000 0 100 200 300 400 Time (s) Figure B.87 ICE P8 – DT Pressure. 500 600 Temperature (°C) VV Wall Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT EMISSION DATE FUS-TN 25-02-2004 SA-SE-R-100 REV. 0 PAGE 117 of 117 443 170.0 423 150.0 403 130.0 ECART Exp 383 110.0 363 90.0 343 70.0 323 50.0 303 30.0 283 0 100 200 300 400 Time (s) Figure B.88 ICE P8 – DT Atmosphere Temperature. 500 10.0 600 Temperature (°C) DT Atmosphere Temperature (K) Associazione ENEA-EURATOM sulla Fusione DOCUMENT