Enhancement of safety analysis capability for a CANDU-6 reactor using RELAP-CANDU/SCAN coupled code system

Kim M; Kim HK; Kim HJ; Hwang SH; Hong IS; Kim CH

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Enhancement of safety analysis capability for a CANDU-6 reactor using RELAP-CANDU/SCAN coupled code system

机译：使用RELAP-CANDU / SCAN耦合代码系统增强CANDU-6反应堆的安全分析能力

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The purpose of this study is the development and verification, of the coupled code system SCAN and RELAP-CANDU for transient analysis of a Canada deuterium uranium (CANDU) reactor. For this purpose, a spatial kinetics calculation module is developed and implemented in SCAN, a three-dimensional (3-D) CANDU pressurized heavy water reactor neutronics design and analysis code. Then, a dynamic linked library of the SCAN code is generated for the integration with RELAP-CANDU.

机译：这项研究的目的是开发和验证耦合代码系统SCAN和RELAP-CANDU，以对加拿大氘铀（CANDU）反应堆进行瞬态分析。为此，在SCAN中开发并实施了空间动力学计算模块，这是三维（3-D）CANDU加压重水反应堆中子学设计和分析代码。然后，生成一个SCAN代码的动态链接库，用于与RELAP-CANDU集成。

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来源
《Nuclear Technology》 |2006年第2期|p. 159-167|共9页
作者
Kim M; Kim HK; Kim HJ; Hwang SH; Hong IS; Kim CH;
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作者单位

Korea Inst Nucl Safety, Regulatory Res Div, Taejon 305600, South Korea;

Seoul Natl Univ, Dept Nucl Engn, Seoul, South Korea;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
RELAP-CANDU/SCAN; coupled code system; safety analysis;

机译：RELAP-CANDU / SCAN;耦合代码系统;安全性分析;

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Enhancement of safety analysis capability for a CANDU-6 reactor using RELAP-CANDU/SCAN coupled code system

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