高灵敏度环境中子剂量当量仪的能量响应计算  

Calculation of Neutron Response for High Sensitivity Environmental Neutron Dose Equivalent Meter

作　　者：魏迎光[1] 刘森林[2] 袁观俊[2] 陈凌[2] 

机构地区：[1]中国人民解放军96411部队,陕西宝鸡721006 [2]中国原子能科学研究院保健物理部,北京102413

出　　处：《原子能科学技术》2006年第B09期134-138,共5页Atomic Energy Science and Technology

摘　　要：利用MCNP4C程序计算1种高灵敏度环境中子剂量当量仪的响应曲线。计算结果在感兴趣能量区间与ICRP建议书中的H^＊（10）曲线符合较好。对MCNP程序计算结果的合理性进行了计算验证。计算结果表明，用MCNP程序优化设计探测器可提高设计效率，并可同时为实验验证提供参考数据。The energy responses of high sensitivity environmental neutron dose equivalent meter was calculated by MCNP4C code. The calculated results are satisfied in interesting neutron energy fields, and the shape of the response curve agrees with H^＊ （10） curve in ICRP 74 report. It is seen that MCNP4C code can be applied to calculate neutron response for high sensitivity environmental neutron dose equivalent meter, and it can raise work efficiency and help to analyze the experimental results.

关 键 词：环境中子 高灵敏度 剂量当量 响应曲线 

分 类 号：TL818.1[核科学技术—核技术及应用]