钠冷快堆堆芯损伤评价方法研究

辐射防护 ›› 2025, Vol. 45 ›› Issue (3): 299-304.

• 核与辐射应急准备与对策 • 上一篇下一篇

钠冷快堆堆芯损伤评价方法研究

梁博宁, 贾林胜, 杨亚鹏, 冯宗洋, 王宁, 刘哲

中国辐射防护研究院,太原 030006

收稿日期:2024-09-18 出版日期:2025-05-20 发布日期:2025-05-21
作者简介:梁博宁(1989—),男,2013年毕业于南华大学核工程与核技术专业,2019年毕业于西安交通大学核科学与技术专业,工学博士,副研究员。E-mail:bnliang_cirp@163.com

Research on assessment method and software development for core damage of sodium cooled fast reactor

LIANG Boning, JIA Linsheng, YANG Yapeng, FENG Zongyang, WANG Ning, LIU Zhe

China Institute for Radiation Protection,Taiyuan 030006

Received:2024-09-18 Online:2025-05-20 Published:2025-05-21

摘要/Abstract

摘要： 本文在压水堆(PWR)堆芯损伤评价方法的基础上,结合霞浦钠冷快堆特性,提出了基于在线监测仪表读数综合评价为主,基于放射性核素取样评价方法为辅的适用于钠冷快堆的堆芯损伤评价模型。所开发的钠冷快堆堆芯损伤评价软件已应用于霞浦钠冷快堆工程。

关键词: 钠冷快堆, 堆芯损伤评价

Abstract: On the basis of core damage assessment method for PWR and combined with the characteristics of 600 MW demonstration sodium cooled fast reactor, this paper proposes an assessment model for core damage of sodium cooled fast reactor based on the comprehensive assessment of on-line monitoring instrument readings as the main model while the radionuclides sampling assessment as the auxiliary model. The developed software of core damage assessment for sodium cooled fast reactor has been applied to the 600 MW demonstration sodium cooled fast reactor project.

Key words: sodium cooled fast reactor, core damage assessment

中图分类号:

TL73

梁博宁, 贾林胜, 杨亚鹏, 冯宗洋, 王宁, 刘哲. 钠冷快堆堆芯损伤评价方法研究[J]. 辐射防护, 2025, 45(3): 299-304.

LIANG Boning, JIA Linsheng, YANG Yapeng, FENG Zongyang, WANG Ning, LIU Zhe. Research on assessment method and software development for core damage of sodium cooled fast reactor[J]. RADIATION PROTECTION, 2025, 45(3): 299-304.

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钠冷快堆堆芯损伤评价方法研究

Research on assessment method and software development for core damage of sodium cooled fast reactor

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