RADIATION PROTECTION ›› 2025, Vol. 45 ›› Issue (1): 62-66.

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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

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

CLC Number: 

  • TL328