Uncertainty and sensitivity analysis of the fission product behaviour in the Phébus FPT1 test with the system code AC2

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-10-01 DOI:10.1016/j.nucengdes.2024.113594
L. Tiborcz , S. Beck
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Abstract

The Phèbus FP (Fission Product) research program, conducted by IRSN and CEA, aimed to improve the understanding of the phenomena governing core melt down, fission product release and transport, as well as the fission product behaviour in the containment. The test facility represents a 900 MWe PWR at a 1/5000 scale. The second test, FPT1, was carried out in 1996 and utilised an Ag-In-Cd alloy control rod. There is a growing interest in Best Estimate Plus Uncertainty analysis both in the research, as well as in the licensing. It has a long-standing history in case of thermal–hydraulic system codes focusing on design basis accidents, but its application is limited on the severe accident domain. In recent times however an increasing attention has been paid to evaluating severe accident codes’ uncertainties. This study presents an uncertainty and sensitivity analysis (UaSA) of the FPT1 test, focusing on fission product behavior modeling within the severe accident code system AC2. The detailed application of the coupled codes ATHLET-CD and COCOSYS in this context is novelty. Detailed description of the methodological and practical approach is provided. The uncertain input parameters chosen and quantified are directly related to the phenomena describing the fission product transport and retention phenomena both in the primary circuit, as well as in the containment, while thermal–hydraulic conditions within the primary circuit were kept as much as possible constant. Finally, the study has been complemented by a sensitivity analysis deriving the Spearman's rank correlation coefficient for each uncertain input parameter.
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利用系统代码 AC2 对费布斯 FPT1 试验中裂变产物行为的不确定性和敏感性分析
由 IRSN 和 CEA 开展的 Phèbus FP(裂变产物)研究计划旨在加深对堆芯熔化、裂变产物释放和运输现象以及安全壳内裂变产物行为的了解。该试验设施是按 1/5000 比例建造的 900 兆瓦压水堆。第二次试验 FPT1 于 1996 年进行,采用了 Ag-In-Cd 合金控制棒。在研究和许可方面,人们对 "最佳估计加不确定性 "分析的兴趣与日俱增。这种方法在热-液压系统规范方面有着悠久的历史,其重点是设计基础事故,但其应用仅限于严重事故领域。然而,近来人们越来越重视评估严重事故规范的不确定性。本研究介绍了 FPT1 试验的不确定性和敏感性分析(UaSA),重点是严重事故代码系统 AC2 中的裂变产物行为建模。在此背景下详细应用耦合代码 ATHLET-CD 和 COCOSYS 是一项创新。详细描述了方法论和实践方法。选择和量化的不确定输入参数与描述初级回路和安全壳中裂变产物运输和滞留现象的现象直接相关,而初级回路中的热-水力条件尽可能保持不变。最后,研究还辅以敏感性分析,得出了每个不确定输入参数的斯皮尔曼等级相关系数。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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