M-C simulation of slow neutron attenuation in boron-containing stainless steel

WEI Qianglin YANG Bo WANG Yi YANG Ting LIU Yibao

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M-C simulation of slow neutron attenuation in boron-containing stainless steel

更新时间：2021-03-05

- M-C simulation of slow neutron attenuation in boron-containing stainless steel
- NUCLEAR TECHNIQUES Vol. 33, Issue 5, (2010)
- 作者机构：
  
  放射性地质与勘探技术国防重点学科实验室,东华理工大学核工程与技术学院
- 作者简介：
- 基金信息：
  
  教育部科技重点项目(208067)资助;江西省教育厅科技项目(GJJ08310)资助;东华理工大学研究生创新基金(DYCA09003)资助
- DOI：
  CLC： O571.5
- Published：01 May 2010
- 稿件说明：
移动端阅览
[1]魏强林,杨波,王毅,杨婷,刘义保.含硼钢对慢中子衰减性能的蒙特卡罗模拟[J].核技术,2010,33(05):367-369.

WEI Qianglin YANG Bo WANG Yi YANG Ting LIU Yibao. M-C simulation of slow neutron attenuation in boron-containing stainless steel[J]. Nuclear techniques, 2010, 33(5): 367-369.
[1]魏强林,杨波,王毅,杨婷,刘义保.含硼钢对慢中子衰减性能的蒙特卡罗模拟[J].核技术,2010,33(05):367-369. DOI：

WEI Qianglin YANG Bo WANG Yi YANG Ting LIU Yibao. M-C simulation of slow neutron attenuation in boron-containing stainless steel[J]. Nuclear techniques, 2010, 33(5): 367-369. DOI：

摘要

用MCNP4C程序模拟了日本研制的KTA-304含硼钢对0.025eV、1eV、1keV慢中子衰减吸收性能

并与传统的SUS304钢进行对比。在充分考虑生产加工条件及材料的防腐蚀性、热延性等因素下比较得出

硼浓度在1.13%左右的含硼钢具有较好的慢中子吸收能力

可有效降低次级γ射线效应

在达到辐射防护要求下可减少材料厚度。计算了不同含硼浓度下含硼钢对不同能量慢中子的衰减系数

为中子屏蔽材料的选择提供了合理依据。另外

还考虑了对中子俘获过程中放出γ射线的防护。

Abstract

In this paper

boron-containing KTA-304 stainless steel for slow neutron absorption and attenuation is studied by Monte Carlo method

and compared with the traditional SUS304 stainless steel.Taking into account some factors

such as processing conditions

corrosion resistance

hot ductility

etc.we may reasonably come to the conclusion that boron content of about 1.13% in the steel has a better absorption capacity to the slow neutron and can effectively reduce the secondary γ-ray effect

meeting the request of radiation protection with reduced material thickness.Besides

slow neutron attenuation coefficient was calculated at different boron concentrations of the steel in different energies

providing a reasonable basis for selecting the neutron shielding materials.The γ-rays released in the neutron capture process were considered

too.

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