Source term uncertainty analysis of filtered containment venting scenarios in Nordic BWR

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-04-08 DOI:10.1016/j.anucene.2025.111406

Sergey Galushin , Govatsa Acharya , Dmitry Grishchenko , Pavel Kudinov

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引用次数: 0

Abstract

Nordic Boiling Water Reactors employ filtered containment venting and ex-vessel debris coolability in the deep pool located under the reactor pressure vessel as cornerstones of their severe accident management strategy.

This paper focuses on the uncertainty analysis of the source term in accident sequences that result in filtered containment venting to the environment using the MELCOR code. The impact of uncertain MELCOR modeling parameters and modeling options on the timing and magnitude of the source term released to the environment has been evaluated in accident sequences initiated by a large break LOCA and SBO.

The performed simulations illustrate the effect of MELCOR modeling parameters and options on the code’s predictions of severe accident progression, event timing, and the magnitude of the source term released to the environment in different accident scenarios. Furthermore, the results highlight the importance of various retention mechanisms that limit the release of fission products into the environment.

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北欧沸水堆过滤容器排放方案源项不确定性分析

北欧沸水反应堆采用过滤式安全壳排气和位于反应堆压力容器下的深池的容器外碎片冷却作为其严重事故管理策略的基石。本文的重点是在事故序列源项的不确定性分析，导致过滤容器排放到环境使用MELCOR代码。不确定的MELCOR建模参数和建模选项对释放到环境中的源项的时间和大小的影响已经在由大型断裂LOCA和SBO引发的事故序列中进行了评估。所进行的模拟说明了MELCOR建模参数和选项对代码预测严重事故进展、事件时间和不同事故场景中释放到环境中的源项的大小的影响。此外，研究结果强调了限制裂变产物释放到环境中的各种保留机制的重要性。

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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来源期刊

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.