在清华大学屏蔽试验堆上实现硼中子俘获治疗  

Realization of BNCT on Tsinghua University shielding experimental reactor

作　　者：貊大卫[1] 蔡庆胜[1] 

机构地区：[1]清华大学核能技术设计研究院

出　　处：《清华大学学报（自然科学版）》1997年第5期58-60,共3页Journal of Tsinghua University(Science and Technology)

摘　　要：硼中子俘获治疗（ＢＮＣＴ）是中子治癌研究中的一个重要课题。将清华大学屏蔽试验堆（９０１堆）的１＃孔道改建成ＢＮＣＴ的治疗孔道实现硼中子俘获治疗。为估价孔道改建的可行性，利用ＭｏｎｔｅＣａｒｌｏ程序进行了计算，并同实验和ＳＮ计算方法的结果进行了对比。其结论是功率为１ＭＷ的９０１反应堆１＃孔完全可以满足ＢＮＣＴ的要求，超热中子通量达１０９ｃｍ－２ｓ－１。Boron neutron capture therapy (BNCT) is a very important subject all over the world recently. Institute of Nuclear Energy Technoloty (INET) plans to rebuild 1 # neutron beam of Tsinghua University shielding experimental reactor for BNCT. Monte Carlo program was used to hold calculation in order to estimate feasibility of rebuilt 1 # neutron beam, and the result of calculation was compared with the results of other calculation method (SN) and experiment. The epithermal neutron flux 10 9 cm -2 ·s -1 was obtained (1 MW power) which is enough for BNCT.

关 键 词：硼中子俘获治疗 屏蔽试验堆 癌 治疗 试验堆 

分 类 号：TL411.307[核科学技术—核技术及应用] R730.55[医药卫生—肿瘤]