CFETR中性束系统验证样机充氢运行辐射分析与初步模拟计算

胡纯栋; 李梦婷; 谢亚红; 陈玉庆

doi:10.11889/j.0253-3219.2018.hjs.41.090603

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CFETR中性束系统验证样机充氢运行辐射分析与初步模拟计算

核能科学与工程 | 更新时间：2021-05-19

- CFETR中性束系统验证样机充氢运行辐射分析与初步模拟计算
- Radiation analysis and simulation of the CFETR neutral beam system prototype with hydrogen beam
- 核技术 2018年41卷第9期文章编号：090603
- 作者机构：
  
  1.中国科学院等离子体物理研究所合肥 230031
  2.中国科学技术大学合肥 230026
- 作者简介：
  
  [ "胡纯栋, 男, 1963年出生, 1999年于中国科学院等离子体物理研究所获博士学位, 主要从事中性束物理与工程研究", "HU Chundong, male, born in 1963, graduated from Institute of Plasma Physics, Chinese Academy of Sciences with a doctoral degree in 1999, focusing on neutral beam physics and engineering research" ]
  陈玉庆, E-mail:chenyq205@ipp.ac.cn CHEN Yuqing, E-mail: chenyq205@ipp.ac.cn
- 基金信息：
  
  国家自然科学基金(11675216);国家自然科学基金(11675215);国家重点研发计划(2017YFE300101);国家自然科学基金(11705229)
- DOI：10.11889/j.0253-3219.2018.hjs.41.090603
  中图分类号： TL69
- 收稿日期：2018-03-02，
  
  修回日期：2018-05-04，
  
  纸质出版日期：2018-09
- 稿件说明：
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胡纯栋, 李梦婷, 谢亚红, 等. CFETR中性束系统验证样机充氢运行辐射分析与初步模拟计算[J]. 核技术, 2018,41(9):090603

Chundong HU, Mengting LI, Yahong XIE, et al. Radiation analysis and simulation of the CFETR neutral beam system prototype with hydrogen beam[J]. Nuclear techniques, 2018, 41(9): 090603
胡纯栋, 李梦婷, 谢亚红, 等. CFETR中性束系统验证样机充氢运行辐射分析与初步模拟计算[J]. 核技术, 2018,41(9):090603 DOI： 10.11889/j.0253-3219.2018.hjs.41.090603.

Chundong HU, Mengting LI, Yahong XIE, et al. Radiation analysis and simulation of the CFETR neutral beam system prototype with hydrogen beam[J]. Nuclear techniques, 2018, 41(9): 090603 DOI： 10.11889/j.0253-3219.2018.hjs.41.090603.

摘要

中国聚变工程实验堆（China Fusion Engineering Test Reactor，CFETR）负离子源中性束系统验证样机正在积极设计筹建中，样机建成后在运行过程中会产生辐射。在设计阶段，仔细分析辐射源的类型、强度和空间分布，为辐射屏蔽设计提供输入数据，从而确保工作人员的辐射安全非常重要。本文通过对样机进行物理和几何建模，然后利用MCNP（Monte Carlo N Particle Transport Code）程序模拟计算200 keV充氢运行的负离子源中性束系统验证样机各关键点的辐射剂量。研究结果为CFETR中性束系统验证样机辐射屏蔽设计提供参考。

Abstract

Background

China fusion engineering test reactor (CFETR) neutral beam injector (NBI) prototype is being actively designed and built. The radiation will be generated during the operation of the prototype. In order to ensure the safety of staff

it is very important to analyze the radiation and types and design the radiation shielding at the design stage.

Purpose

To study the radiation dose of the CFETR neutral beam test facility with hydrogen beam energy of 200 keV.

Methods

According to the established model of physics parameter and geometry

the radiation dose of the key points of the negative ion based neutral beam injector system with the beam energy of 200 keV was simulated by Monte Carlo N particle transport code (MCNP).

Results

The vacuum wall has some self-shielding effects

but it does not decrease the dose to the dose limits setting by the International Atomic Energy Agency (IAEA).

Conclusion

This result can provide important reference for the design of radiation shielding for CFETR neutral beam system.

关键词

Keywords

references

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