Comparative analysis of CANDU severe accident using CAISER

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Annals of Nuclear Energy Pub Date : 2025-10-17 DOI:10.1016/j.anucene.2025.111931

Jun-young Kang Ph.D., Yong Mann Song, Dong Gun Son, Keun Sang Choi, Jong Yeob Jung, Jun Ho Bae, Byeonghee Lee

引用次数: 0

Abstract

CAISER (CANDU Advanced Integrated SEveRe accident analysis) is the recently developed the system code to evaluate the severe accident of CANDU plant and models the CANDU reactor core, incorporating 380 fuel channels and 37 fuel pins within a Cartesian-coordinate node system. It enables detailed assessments of mass and temperature distributions inside fuel channels including core degradation and relocation. CAISER code is coupled with the reactor thermal–hydraulic module (MARS-KS), the ex-vessel containment module (CONTAIN) and source term module (SIRIUS) using dynamic linked libraries. Present study evaluated the reference scenario of severe accident from IAEA-CRP (TECDOC-1727), benchmarking severe accident simulation tools for CANDU applications. Calculated results by CAISER are compared with that of IAEA-CRP and MAAP-ISAAC v4.03 and are discussed from the in-calandria to the ex-calandria phenomena.

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应用CAISER对CANDU严重事故进行对比分析

CAISER （CANDU Advanced Integrated SEveRe accident analysis, CANDU Advanced Integrated SEveRe accident analysis）是最近开发的CANDU核电厂严重事故评估系统代码，用于对CANDU堆芯进行建模，在直角坐标节点系统中包含380个燃料通道和37个燃料销。它可以详细评估燃料通道内的质量和温度分布，包括堆芯降解和重新安置。CAISER代码使用动态链接库与反应堆热压模块（MARS-KS）、前容器密封模块（CONTAIN）和源项模块（SIRIUS）耦合。本研究评估了来自IAEA-CRP （TECDOC-1727）的严重事故参考情景，这是CANDU应用的基准严重事故模拟工具。将CAISER的计算结果与IAEA-CRP和MAAP-ISAAC v4.03的计算结果进行了比较，并从历内现象到历外现象进行了讨论。

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.