堆芯损伤评价中安全壳内放射性核素浓度的计算

辐射防护通讯 ›› 2014, Vol. 34 ›› Issue (2): 12-15.

堆芯损伤评价中安全壳内放射性核素浓度的计算

李文静, 龙亮

中国核电工程有限公司, 北京, 100840

收稿日期:2014-01-12 出版日期:2014-04-20 发布日期:2025-02-26
作者简介:李文静(1989- ),女, 2011年毕业于清华大学工程物理系核科学与核技术专业,学士; 中国核电工程有限公司核能科学与工程专业硕士在读。

Calculation of Containment Radionuclide Concentration in Core Damage Assessment

Li Wenjing, Long Liang

China Nuclear Power Engineering Co. Ltd., Beijing, 100840

Received:2014-01-12 Online:2014-04-20 Published:2025-02-26

摘要/Abstract

摘要： 安全壳内放射性核素浓度的计算是确定安全壳辐射剂量率的重要环节,而安全壳辐射剂量率是堆芯损伤评价的重要参数之一。本文利用ORIGEN2程序,采用简化分析法和间接计算法分别对事故后3种典型核素在安全壳内的浓度进行分析计算,并对两种方法的可用性进行了讨论。根据分析可知,间接计算法能够更好的模拟核素的释放、衰变以及相互转化过程,建议在事故早期堆芯损伤评价过程中使用。但是若考虑事故发生较长时间后的安全壳内核素浓度,短半衰期核素影响已经很小,简化分析法是可用的。

关键词: 堆芯损伤, 安全壳辐射剂量率, 放射性核素浓度, ORIGEN2

Abstract: Calculation of containment radionuclide concentration is an important part of estimating containment radiation dose rate, and the latter is a primary parameter for core damage assessment. This paperprovides the calculation of concentration of three typical nuclides within containment post-accident in both simplified analytical method and indirect methodwith ORIGEN2 code. The results show that the indirect method can simulate the release and decay of radionuclides and the transformation among them, and suggests it can be used in the early core damage assessment. But if the containment radionuclide concentration is evaluated after a long time since the accident, whenthe nuclides with short half-lives have little effects on the result, the simplified method is appropriate.

Key words: Core damage assessment, Containment radiation dose rate, Containment radionuclide concentration, ORIGEN2 model

中图分类号:

TL364⁺.4

李文静, 龙亮. 堆芯损伤评价中安全壳内放射性核素浓度的计算[J]. 辐射防护通讯, 2014, 34(2): 12-15.

Li Wenjing, Long Liang. Calculation of Containment Radionuclide Concentration in Core Damage Assessment[J]. RADIATION PROTECTION BULLETIN, 2014, 34(2): 12-15.