SFR堆无保护失流事故的热液多尺度工具VVUQ

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY
N. Marie, Simon Li, A. Marrel, M. Marquès, S. Bajard, A. Tosello, Jorge Perez, Baptiste Grosjean, A. Gerschenfeld, M. Anderhuber, Chotaire Geffray, Y. Gorsse, G. Mauger, L. Matteo
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引用次数: 2

摘要

在法国第四代钠冷快堆安全评估的框架内,对VVUQ(验证、确认、不确定性量化)进行了方法学研究,以证明CEA的热工水力科学计算工具(sct)在这类反应堆的设计和安全研究中是有效和可操作的。这种基于vvuq的资格是法国核安全局(NSA)的监管要求。本文从NSA的要求出发,介绍了VVUQ方法在SFR事故暂态中的应用现状。这是第一个实用的、可逐步改进的方法。由于SCT适用于给定场景下的给定版本,因此选择了与完全无保护的站点停电相关的瞬态。由于它是一个非常复杂的多尺度瞬变,因此使用SCT MATHYS(它是系统尺度上的CATHARE2工具,组件尺度上的TrioMC工具和局部尺度上的TrioCFD工具的耦合)。本文介绍了VVUQ的初步应用,以确定该工具对选定的瞬态。此外,这项工作强调了设计和研发方面的一些反馈,这些反馈应该在未来得到解决,以改进SCT。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
VVUQ of a thermal-hydraulic multi-scale tool on unprotected loss of flow accident in SFR reactor
Within the framework of the French 4th-generation Sodium-cooled Fast Reactor safety assessment, methodology on VVUQ (Verification, Validation, Uncertainty Quantification) is conducted to demonstrate that the CEA's thermal-hydraulic Scientific Computation Tools (SCTs) are effective and operational for design and safety studies purposes on this type of reactor. This VVUQ-based qualification is a regulatory requirement from the French Nuclear Safety Authority (NSA). In this paper, the current practice of VVUQ approach application for a SFR accidental transient is described with regard to the NSA requirements. It constitutes the first practical, progressively improvable approach. As the SCT is qualified for a given version on a given scenario, the transient related to a total unprotected station blackout has been selected. As it is a very complex multi-scale transient, the SCT MATHYS (which is a coupling of the CATHARE2 tool at system scale, TrioMC tool at component scale and TrioCFD tool at local scale) is used. This paper presents the preliminary VVUQ application to the qualification of this tool on this selected transient. In addition, this work underlines some feedback on design and R&D aspects that should be addressed in the future to improve the SCT.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
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