严重事故领域的逆不确定性量化：在裂变产物释放中的应用

IF 2.1 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Nuclear Engineering and Design Pub Date : 2025-03-10 DOI:10.1016/j.nucengdes.2025.113954

G. Tinfena , M. Angelucci , L. Sargentini , S. Paci , L.E. Herranz

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引用次数: 0

摘要

本文介绍了由CSNI/WGAMA在SAPIUM活动中提出的逆不确定性量化（IUQ）方法在严重事故（SA）领域的开创性应用。在SEAKNOT-EU项目框架下，这种系统方法已用于裂变产物释放（FPR）的不确定度量化，特别是根据MELCOR代码估计的铯分数。我们对60多个实验进行了分析，根据充分性分析的建议，根据实验的完备性和代表性进行了选择。利用IUQ CIRCE方法，估计了修正CORSOR-Booth模型的不确定范围，并证明了与数据库的一致性。最后，根据PHEBUS-FPT1记录的在线实验数据验证了不确定度表征。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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Inverse uncertainty Quantification in the Severe accident Domain: Application to Fission Product release

This paper presents a pioneering application of Inverse Uncertainty Quantification (IUQ) methodology, proposed by CSNI/WGAMA in the SAPIUM activity, within the Severe Accident (SA) domain. Framed under the SEAKNOT-EU project, such a systematic approach has been used for uncertainty quantification of the Fission Product Release (FPR), particularly the cesium fractional one, as estimated by the MELCOR code. More than 60 experiments have been analyzed and some of them selected based on their completeness and representativeness, as recommended by the adequacy analysis. By using the IUQ CIRCE method, the so called Revised CORSOR-Booth model uncertainty range has been estimated and proved consistent with the database. Finally, the uncertainty characterization has been validated against on-line experimental data recorded in PHEBUS-FPT1.

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来源期刊

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.