铅冷反应堆容器外辐射场特性分析

辐射防护 ›› 2024, Vol. 44 ›› Issue (S1): 13-17.

铅冷反应堆容器外辐射场特性分析

翟梓安^1,2, 吴怡睿^1,2, 苗建新^1,2, 王霜^1,2, 李文瀚^1,2, 邓理邻^1,2, 陈鑫^1,2, 温兴坚^1,2, 余鸿^1,2

1.核反应堆技术全国重点实验室,成都 610213;
2.中国核动力研究设计院,成都 610213

收稿日期:2023-11-24 出版日期:2024-11-20 发布日期:2024-12-26
作者简介:翟梓安(1994—),男,2019年6月毕业于西安交通大学核科学与技术专业,获硕士学位,工程师。E-mail:zazhai_2021@163.com

Analysis on radiation field characteristics outside lead-cooled reactor vessel

ZHAI Zi′an^1,2, WU Yirui^1,2, MIAO Jianxin^1,2, WANG Shuang^1,2, LI Wenhan^1,2, DENG Lilin^1,2, CHEN Xin^1,2, WEN Xingjian^1,2, YU Hong^1,2

1. National Key Laboratory of Nuclear Reactor Technology, Chengdu 610213;
2. Nuclear Power Institute of China, Chengdu 610213

Received:2023-11-24 Online:2024-11-20 Published:2024-12-26

摘要/Abstract

摘要： 铅冷反应堆作为第四代反应堆类型之一备受世界关注。由于铅冷却剂的中子、γ屏蔽性能与水截然不同,导致铅冷堆不同状态下反应堆容器外的辐射场情况与压水堆均有较大差别,压水堆的屏蔽设计经验不能直接应用于铅冷反应堆屏蔽设计。为满足第四代反应堆先进经济的屏蔽设计要求,屏蔽设计也需要更加精细和高效,因此开展反应堆容器外辐射场特性分析具有重要意义。本文选取典型铅冷反应堆侧部结构,建立一维计算模型,利用RMC程序详细分析了正常运行及停堆状态下铅冷反应堆容器外围辐射场的情况。首先,通过对比分析铅冷反应堆与压水堆正常运行时容器外围中子、γ通量密度结果,明确正常运行时屏蔽设计需要解决的主要矛盾。同时,通过分析外围γ射线的主要贡献来源,确定γ射线产生位置和产生原因。然后,通过对比分析铅冷反应堆与压水堆在停堆状态下的堆芯源项和反应堆容器活化源项,以及停堆后反应堆容器外的辐射场结果,确定铅冷反应堆停堆状态下的外围辐射场的主要贡献来源。最后,结合铅冷反应堆正常运行及停堆状态的辐射场特性,提出了铅冷反应堆屏蔽设计的思路方法。本文得到的铅冷反应堆辐射场特性分析结论适用于快谱、混合谱铅冷反应堆的屏蔽设计,为铅冷反应堆高效、经济的屏蔽设计打下理论基础。

关键词: 铅冷反应堆, 辐射场特性, 活化计算

Abstract: Lead-cooled reactor, one of the fourth generation nuclear power reactor technology, attracts great attention from the world. Due to the significant differences in neutron and γ shielding capabilities between lead coolant and water, radiation field outside the vessel of a lead-cooled reactor differs greatly from that of a pressurized water reactor (PWR). Therefore, the shield design experience from PWRs can't be directly applied to the shield design of lead-cooled reactors. In order to meet the economic shield design requirements of the fourth generation reactors, shield design also needs to be more precise and efficient. Therefore, conducting an analysis of the radiation field characteristics outside the reactor vessel is of great significance. In this study, a typical radial structure of a lead-cooled reactor is chosen, and a 1D computational model is established to analyze the radiation field outside the reactor vessel under normal operation and shutdown conditions by using the RMC program. Firstly, by comparing and analyzing the neutron and γ flux outside the vessel during normal operation of the lead-cooled reactor and PWR, the main contradictions that the shield design needs to be solved during normal operation are identified. At the same time, by analyzing the main sources of γ outside the vessel, the locations and causes of γ generation are determined. Then, the main contributors to the radiation field outside the vessel during shutdown of the lead-cooled reactor are determined by comparing and analyzing the core source terms and reactor vessel activation source terms as well as radiation fields results outside the vessel. Finally, based on the radiation field characteristics of the lead-cooled reactor during normal operation and shutdown, methods for shield design of lead-cooled reactors are proposed. The conclusions in this study are applicable to the shield design of lead-cooled reactors, laying a theoretical foundation for efficient and economical shield design in lead-cooled reactors.

Key words: lead-cooled reactor, radiation field characteristics, activation source calculation

中图分类号:

O572.2

翟梓安, 吴怡睿, 苗建新, 王霜, 李文瀚, 邓理邻, 陈鑫, 温兴坚, 余鸿. 铅冷反应堆容器外辐射场特性分析[J]. 辐射防护, 2024, 44(S1): 13-17.

ZHAI Zi′an, WU Yirui, MIAO Jianxin, WANG Shuang, LI Wenhan, DENG Lilin, CHEN Xin, WEN Xingjian, YU Hong. Analysis on radiation field characteristics outside lead-cooled reactor vessel[J]. RADIATION PROTECTION, 2024, 44(S1): 13-17.