反应堆235U裂变源辐射防护材料的优化设计

计算物理 ›› 2017, Vol. 34 ›› Issue (1): 73-81.

反应堆²³⁵U裂变源辐射防护材料的优化设计

杨师俨, 何曼丽, 蒋丹枫, 王国辉, 苑超, 戴耀东

南京航空航天大学材料科学与技术学院, 南京 210016

收稿日期:2015-11-15 修回日期:2016-03-07 出版日期:2017-01-25 发布日期:2017-01-25
通讯作者: 戴耀东,E-mail:yd_dai@126.com
作者简介:杨师俨(1991-),男,硕士研究生,主要从事防护材料研究,E-mail:yangshiyan_1991415@163.com
基金资助:
高等学校博士学科点专项科研基金（2012321811008）；江苏省产学研联合创新资金（新型非金属基柔性核辐射防护材料及防护装备研发）及江苏高校优势学科建设工程资助项目

Optimization Design of Radiation Shielding Materials for ²³⁵U Fission Source in Reactor

YANG Shiyan, HE Manli, JIANG Danfeng, WANG Guohui, YUAN Chao, DAI Yaodong

College of Material Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing 210016, China

Received:2015-11-15 Revised:2016-03-07 Online:2017-01-25 Published:2017-01-25

摘要/Abstract

摘要： 以热中子反应堆²³⁵U裂变源为辐射源，利用MCNP程序对其能谱进行模拟并研究其辐射防护，结果表明对²³⁵U裂变源所发射的能量高于3MeV的瞬发中子，重金属具有良好的屏蔽效果，而对于能量低于1MeV的中子，轻氢材料的防护效果更好；W/LiH，W/B₄C，TiH₂/W三种复合材料当质量比满足：W：LiH=19：1，W：B₄C=9：1，W：TiH₂=3：1时材料的屏蔽效果最佳；通过遗传算法结合MCNP模拟，得到W/TiH₂/B₄C，TiH₂/Cu/Gd，TiH₂/B₄C/Gd三种复合材料的最优组分配比，源每次裂变产生的粒子穿过这三种材料后在等效组织中造成的剂量当量率（10^-11Sv·h^-1）与材料厚度呈指数下降关系，三种材料分别可近似为1.071exp（-0.187 8x），1.077exp（-0.166 2x）和1.608exp（-0.171 9x），x为材料厚度（cm）.

关键词: 蒙特卡罗方法, 反应堆, n-γ混合场, 屏蔽材料

Abstract: With ²³⁵U fission source in thermal neutron reactor as radiation source, MCNP code is employed to simulate energy spectrum and to study shielding protect.It shows that for prompt neutron, emitting by ²³⁵U fission source, with energy more than 3 MeV, heavy metals materials have better shielding effect.However, light hydrogen materials performance better for neutrons with energy below 1MeV.For compounds-W/LiH, W/B₄C and TiH₂/W, shielding effect is best as weight ratios are W:LiH=19:1, W:B₄C=9:1, W:TiH₂=3:1.GA combined with MCNP code is employed to search optimized design of compounds, W/TiH₂/B₄C, TiH₂/Cu/Gd and TiH₂/B₄C/Gd, respectively.Weight fractions are calculated as shielding effect performance is best.Exponential decay relations between dose equivalent rate (10^-11Sv·h^-1) in tissues caused by neutron and gamma rays penetrating materials and thickness of materials can be expressed as 1.071exp (-0.187 8x), 1.077exp (-0.166 2x) and 1.608exp (-0.171 9x), respectively, where x is thickness of material in cm.

Key words: Monte Carlo method, reactor, n-γ rays, shielding material

中图分类号:

杨师俨, 何曼丽, 蒋丹枫, 王国辉, 苑超, 戴耀东. 反应堆²³⁵U裂变源辐射防护材料的优化设计[J]. 计算物理, 2017, 34(1): 73-81.

YANG Shiyan, HE Manli, JIANG Danfeng, WANG Guohui, YUAN Chao, DAI Yaodong. Optimization Design of Radiation Shielding Materials for ²³⁵U Fission Source in Reactor[J]. CHINESE JOURNAL OF COMPUTATIONAL PHYSICS, 2017, 34(1): 73-81.

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反应堆²³⁵U裂变源辐射防护材料的优化设计

Optimization Design of Radiation Shielding Materials for ²³⁵U Fission Source in Reactor

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