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PGNAA系统中D-T中子管的慢化装置优化设计

黄红 李锐 王琦标 庹先国 杨剑波 王旭

黄红 李锐 王琦标 庹先国 杨剑波 王旭. PGNAA系统中D-T中子管的慢化装置优化设计[J]. 原子核物理评论, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
引用本文: 黄红 李锐 王琦标 庹先国 杨剑波 王旭. PGNAA系统中D-T中子管的慢化装置优化设计[J]. 原子核物理评论, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
HUANG Hong. Optimal and Design of D-T Neutron Generator Moderation Setup in PGNAA System[J]. Nuclear Physics Review, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
Citation: HUANG Hong. Optimal and Design of D-T Neutron Generator Moderation Setup in PGNAA System[J]. Nuclear Physics Review, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077

PGNAA系统中D-T中子管的慢化装置优化设计

doi: 10.11804/NuclPhysRev.33.01.077

Optimal and Design of D-T Neutron Generator Moderation Setup in PGNAA System

  • 摘要: 为了提高PGNAA系统中D-T中子管的中子慢化效率,获得更高的热中子产额,借助蒙特卡罗模拟,确定了以铅为中子反射层、5个聚乙烯层和铅层相互交替作为中子慢化层、碳化硼含量为3%的含硼聚乙烯作为中子吸收层以及铅作为γ屏蔽层的中子慢化装置模型。针对中子产额为3×107 n/s 的D-T中子管,该慢化装置输出面低于5 eV中子通量可达5.28×106 n/s,占总中子通量的30.8%,有效提高了中子慢化效率。经过验证模拟结果能够满足实验要求。

    To improve the moderating efficiency of D-T Neutron Generator in PGNAA system, and get higher thermal neutron yield, the Monte Carlo code MCNP was used to optimize the moderation setup. The lead was selected as neutron reflector and gamma absorber, 5 polyethylene layers and 4 lead layers constituted the neutron moderator and 3% boron-doping polyethylene was selected as neutron absorber. For the yield of 3107 n/s D-T Neutron Generator, this moderation setup can provide a yield of lower than 5 eV of 5.28106 n/s, accounting for 30.8% of total neutron yield, dramatically improves the moderating efficiency. It is proved that the simulation results can satisfy the requirement of PGNAA system by preliminary experimental verification.
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出版历程
  • 收稿日期:  2015-10-19
  • 刊出日期:  2016-03-20

PGNAA系统中D-T中子管的慢化装置优化设计

doi: 10.11804/NuclPhysRev.33.01.077

摘要: 为了提高PGNAA系统中D-T中子管的中子慢化效率,获得更高的热中子产额,借助蒙特卡罗模拟,确定了以铅为中子反射层、5个聚乙烯层和铅层相互交替作为中子慢化层、碳化硼含量为3%的含硼聚乙烯作为中子吸收层以及铅作为γ屏蔽层的中子慢化装置模型。针对中子产额为3×107 n/s 的D-T中子管,该慢化装置输出面低于5 eV中子通量可达5.28×106 n/s,占总中子通量的30.8%,有效提高了中子慢化效率。经过验证模拟结果能够满足实验要求。

To improve the moderating efficiency of D-T Neutron Generator in PGNAA system, and get higher thermal neutron yield, the Monte Carlo code MCNP was used to optimize the moderation setup. The lead was selected as neutron reflector and gamma absorber, 5 polyethylene layers and 4 lead layers constituted the neutron moderator and 3% boron-doping polyethylene was selected as neutron absorber. For the yield of 3107 n/s D-T Neutron Generator, this moderation setup can provide a yield of lower than 5 eV of 5.28106 n/s, accounting for 30.8% of total neutron yield, dramatically improves the moderating efficiency. It is proved that the simulation results can satisfy the requirement of PGNAA system by preliminary experimental verification.

English Abstract

黄红 李锐 王琦标 庹先国 杨剑波 王旭. PGNAA系统中D-T中子管的慢化装置优化设计[J]. 原子核物理评论, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
引用本文: 黄红 李锐 王琦标 庹先国 杨剑波 王旭. PGNAA系统中D-T中子管的慢化装置优化设计[J]. 原子核物理评论, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
HUANG Hong. Optimal and Design of D-T Neutron Generator Moderation Setup in PGNAA System[J]. Nuclear Physics Review, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077
Citation: HUANG Hong. Optimal and Design of D-T Neutron Generator Moderation Setup in PGNAA System[J]. Nuclear Physics Review, 2016, 33(1): 77-81. doi: 10.11804/NuclPhysRev.33.01.077

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