辐射防护 ›› 2025, Vol. 45 ›› Issue (1): 62-66.

• 辐射防护方法 • 上一篇    下一篇

基于边界表示模型的点核积分程序的开发与应用

唐松乾, 温兴坚, 吕焕文, 李文瀚, 苗建新, 陈鑫   

  1. 中国核动力研究设计院 核反应堆技术全国重点实验室, 成都 610213
  • 收稿日期:2024-03-18 出版日期:2025-01-20 发布日期:2025-01-21
  • 作者简介:唐松乾(1988—),男,2013年硕士毕业于哈尔滨工程大学核能科学与工程专业。E-mail: tcdsg0@163.com

Development and application for point kernel computer code based on boundary representation geometry

TANG Songqian, WEN Xingjian, LV Huanwen, LI Wenhan, MIAO Jianxin, CHEN Xin   

  1. National Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, Chengdu 610213
  • Received:2024-03-18 Online:2025-01-20 Published:2025-01-21

摘要: 点核积分方法是屏蔽设计中最常用的方法之一。为了克服传统点核积分方法因无法直接使用辐射防护现场基于边界表示(Brep,boundary representation)几何需重新建模而出现模型描述复杂且易出错的问题,本次研究开发了直接基于Brep几何的点核积分方法,可直接基于现场CAD模型进行辐射场计算,提升了点核积分方法的几何适应能力。使用某乏燃料运输容器基准问题对程序的准确性进行了验证,验证结果表明程序的计算结果与QAD程序吻合良好,使用华龙一号的主回路设备间屏蔽问题对程序的复杂几何适应能力进行验证,验证结果表明程序具备复杂场景的三维辐射场计算能力。

关键词: 点核积分方法, Brep几何, 三维辐射场

Abstract: The point kernel method is one of the most commonly used methods in shielding design. In order to overcome the problem in error-prone traditional point kernel code because of geometric description caused by not re-modeled directly using radiation protection field, a point-kernel code based on boundary representation geometry was developed. The accuracy of the program was validated using the OECD benchmark for spent fuel transport cask. The results show that the calculation results of this program are in good agreement with QAD. The complex geometric adaptability of the program was validated by using ACP1000 shielding calculation model for main equipment room. The results show that the program has the ability to calculate three dimensional radiation field in complex problem.

Key words: point kernel method, boundary representation geometry, three dimensional radiation field

中图分类号: 

  • TL328