【作者】 魏迎光； 刘森林； 袁观俊； 陈凌；

【Author】 WEI Ying-guang , LIU Sen-lin, YUAN Guan-jun, CHEN Ling ( 96411 Unit of PLA, Baoji 721006, China; China Institute of Atomic Energy, P.O. Box 275-24, Beijing 102413, China)

【机构】 中国人民解放军96411部队； 中国原子能科学研究院保健物理部；

【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。更多还原

【Abstract】 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.更多还原