Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package

被引:3
|
作者
Brumm, S. [1 ]
Gabrielli, F. [2 ]
Espinoza, V. Sanchez [2 ]
Stakhanova, A. [2 ]
Groudev, P. [3 ]
Petrova, P. [3 ]
Vryashkova, P. [3 ]
Ou, P. [4 ]
Zhang, W. [4 ]
Malkhasyan, A. [5 ]
Herranz, L. E. [6 ]
Ferrer, R. Iglesias [6 ]
Angelucci, M. [6 ,25 ]
Berdai, M. [7 ]
Mascari, F. [8 ]
Agnello, G. [8 ,26 ]
Sevbo, O. [9 ]
Iskra, A. [9 ]
Quiroga, V. Martinez [10 ]
Nudi, M. [11 ]
Hoefer, A. [12 ]
Pauli, E. -m. [12 ]
Beck, S. [13 ]
Tiborcz, L. [13 ]
Coindreau, O. [14 ]
Clark, G. [15 ]
Lamont, I. [15 ]
Zheng, X. [16 ]
Kubo, K. [16 ]
Lee, B. [17 ]
Valincius, M. [18 ]
Malicki, M. [19 ]
Lind, T. [19 ]
Vorobyov, Y. [20 ]
Kotsuba, O. [20 ]
Di Giuli, M. [21 ]
Ivanov, I. [22 ]
D'Onorio, M. [23 ]
Giannetti, F. [23 ]
Sevon, T. [24 ]
机构
[1] European Commiss Joint Res Ctr JRC, Westerduinweg 3, NL-1755 LE Petten, Netherlands
[2] Karlsruhe Inst Technol KIT, Hermann von Helmholtzpl 1, D-76344 Eggenstein Leopoldshafen, Germany
[3] Bulgarian Acad Sci INRNE BAS, Inst Nucl Res & Nucl Energy, Tzarigradsko Chaussee 72, Sofia 1784, Bulgaria
[4] CNPRI, 21-F Sci & Technol Bldg,Shangbuzhong Rd, Shenzhen, Peoples R China
[5] BEL V, Rue Walcourt 148, B-1070 Anderlecht, Belgium
[6] CIEMAT, Dept Energy, Nucl Safety Res Unit, Avda Complutense 40,Edificio 12-P0-13, Madrid 28040, Spain
[7] CNSC, 280 Slater St, Ottawa, ON K1P 5S9, Canada
[8] ENEA, Via Martiri Monte Sole 4, I-40129 Bologna, Italy
[9] Energorisk LLC, Off 141,7 Simii Steshenkiv Str, UA-03148 Kyiv, Ukraine
[10] Energy Sftware SL, ENSO, Catalunya 13, Taradell 08440, Barcelona, Spain
[11] EPRI, 1300 West WT Harris Blvd, Charlotte, NC 28262 USA
[12] Framatome GmbH, Paul Gossen Str 100, D-91052 Erlangen, Germany
[13] Gesell Anlagen & Reaktorsicherheit GRS gGmbH, Schwertnergasse 1, D-50667 Cologne, Germany
[14] IRSN, Ctr Cadarache, BP 3, F-131115 St Paul Les Durance, France
[15] Jacobs, 305 Bridgewater Pl,Birchwood Pk, Warrington WA3 6XG, England
[16] Japan Atom Energy Agcy JAEA, 2-4 Shirakata, Naka, Ibaraki 3191195, Japan
[17] Korea Atom Energy Res Inst KAERI, Daedeokdaero 989-111, Daejeon 34057, South Korea
[18] Lithuanian Energy Inst LEI, Breslaujos Str 3, LT-44403 Kaunas, Lithuania
[19] Paul Scherrer Inst PSI, Forschungsstr 111, CH-5232 Villigen, Switzerland
[20] SSTC NRS, 35-37 V Stusa St, UA-03142 Kyiv, Ukraine
[21] Severe Accid Grp, Tractebel ENGIE, Ave S Bolivar 34-36, Brussels, Belgium
[22] Tech Univ Sofia TUS, 8 St Kliment Ohridski Blvd,Bl 12, Sofia 1000, Bulgaria
[23] Sapienza Univ Rome, DIAEE, Corso Vittorio Emanuele II 244, I-00186 Rome, Italy
[24] VTT Tech Res Ctr Finland, Kivimiehentie 3, Espoo, Finland
[25] Univ Pisa, Pisa, Italy
[26] Univ Palermo, Palermo, Italy
关键词
Nuclear reactor; Severe accident; Modelling; Uncertainty quantification; MUSA; Source term;
D O I
10.1016/j.anucene.2024.110962
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The recently completed Horizon-2020 project "Management and Uncertainties of Severe Accidents (MUSA)" has reviewed uncertainty sources and Uncertainty Quantification methodology for assessing Severe Accidents (SA), and has made a substantial effort at stimulating uncertainty applications in predicting the radiological Source Term of reactor and Spent Fuel Pool accident scenarios. The key motivation of the project has been to bring the advantages of the Best Estimate Plus Uncertainty approach to the field of Severe Accident modelling. With respect to deterministic analyses, expected gains are avoiding adopting conservative assumptions, identifying uncertainty bands of estimates, and gaining insights into dominating uncertain parameters. Also, the benefits for understanding and improving Accident Management were to be explored. The reactor applications brought together a large group of participants that set out to apply uncertainty analysis (UA) within their field of SA modelling expertise - in particular reactor types, but also SA code used (ASTEC, MELCOR, MAAP, RELAP/SCDAPSIM), uncertainty quantification tools used (DAKOTA, SUSA, URANIE, self-developed tools based on Python code), detailed accident scenarios, and in some cases SAM actions. The setting up of the analyses, challenges faced during that phase, and solutions explored, are described in Brumm et al. ANE 191 (2023). This paper synthesizes the reactor-application work at the end of the project. Analyses of 23 partners are presented in different categories, depending on whether their main goal is/are (i) uncertainty bands of simulation results; (ii) the understanding of dominating uncertainties in specific sub-models of the SA code; (iii) improving the understanding of specific accident scenarios, with or without the application of SAM actions; or, (iv) a demonstration of the tools used and developed, and of the capability to carry out an uncertainty analysis in the presence of the challenges faced. A cross-section of the partners' results is presented and briefly discussed, to provide an overview of the work done, and to encourage accessing and studying the project deliverables that are open to the public. Furthermore, the partners' experiences made during the project have been evaluated and are presented as good practice recommendations. The paper ends with conclusions on the level of readiness of UA in SA modelling, on the determination of governing uncertainties, and on the analysis of SAM actions.
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页数:16
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