期刊论文

Calculation and analysis of neutron and gamma shielding performance based on boron-containing stainless steel materials

Song, Y.

中文

核技术

0253-3219

2019

42

9

090201

10.11889/j.0253-3219.2019.hjs.42.090201

Supported by National Key Laboratory Open-end Fund for High-end Equipment Light Alloy Casting Technology (No.2018SYS04), College Students Research Learning and Innovative Experimental Project in University of South China (No.2018XJXZ043)

本校为第一机构

采用蒙特卡罗粒子输运程序与燃耗计算分析程序相结合（MCNP5/ORIGEN2.1）的方法对辐射防护不锈钢材料屏蔽性能和活化产物进行了综合计算分析。结合辐射屏蔽设计结构优化方法和性能计算的具体要求,给出了中子/γ综合屏蔽性能分析评价方法,针对核反应堆单层外照射三层屏蔽结构简化模型,模拟计算了硼不锈钢和普通不锈钢材料对中子/γ混合辐射场的中子、光子、（n,γ）反应产生的光子、材料内二次活化产物光子的屏蔽效果,并对防护材料的综合屏蔽性能进行了评价。

[Background]： The simulation calculation of shielding performance of radiation protection materials at home and abroad is usually limited to one simulation of the Monte Carlo method, while the fine-grained calculation of gamma ray shielding of secondary products is less. [Purpose]： This study aims to analyze shielding performance and activation products of boron-containing stainless steel materials. [Methods]： Monte Carlo particle transport program combined with fuel consumption calculation and analysis program (MCNP5/ORIGEN2.1) was employed...