严重事故反应堆建模的不确定性量化:MUSA 反应堆应用工作包的结果和结论

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S. Brumm , F. Gabrielli , V. Sanchez Espinoza , A. Stakhanova , P. Groudev , P. Petrova , P. Vryashkova , P. Ou , W. Zhang , A. Malkhasyan , L.E. Herranz , R. Iglesias Ferrer , M. Angelucci , M. Berdaï , F. Mascari , G. Agnello , O. Sevbo , A. Iskra , V. Martinez Quiroga , M. Nudi , T. Sevon
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引用次数: 0

摘要

最近完成的 "地平线-2020 "项目 "严重事故的管理和不确定性(MUSA)"审查了评估严重事故(SA)的不确定性来源和不确定性量化方法,并在促进不确定性应用于预测反应堆和乏燃料池事故情景的辐射源终端方面做出了巨大努力。就确定性分析而言,预期收益是避免采用保守假设,确定估算的不确定性带,并深入了解主要的不确定参数。反应堆应用汇集了一大批参与者,他们在各自的 SA 建模专业领域内应用不确定性分析 (UA),特别是反应堆类型,以及所使用的 SA 代码(ASTEC、MELCOR、MAAP、RELAP/SCDAPSIM)、所使用的不确定性量化工具(DAKOTA、SUSA、URANIE、基于 Python 代码的自主开发工具)、详细的事故情景和某些情况下的 SAM 行动。Brumm et al. ANE 191 (2023)中介绍了分析的设置、该阶段面临的挑战以及探索的解决方案。23 个合作伙伴的分析结果按其主要目标分为不同类别:(i) 模拟结果的不确定性带;(ii) 了解 SA 代码特定子模型中的主要不确定性;(iii) 在应用或不应用 SAM 行动的情况下,提高对特定事故情景的了解;或 (iv) 展示所使用和开发的工具,以及在面临挑战时进行不确定性分析的能力。对合作伙伴的成果进行了横向介绍和简要讨论,以概述已完成的工作,并鼓励获取和研究向公众开放的项目成果。此外,还对合作伙伴在该项目中取得的经验进行了评估,并将其作为良好实践建议进行介绍。本文最后就普遍获得在可持续性评估建模中的准备程度、管理不确定性的确定以及可持续性评估行动的分析得出了结论。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Uncertainty quantification for severe-accident reactor modelling: Results and conclusions of the MUSA reactor applications work package
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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来源期刊
Annals of Nuclear Energy
Annals of Nuclear Energy 工程技术-核科学技术
CiteScore
4.30
自引率
21.10%
发文量
632
审稿时长
7.3 months
期刊介绍: Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.
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