基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计

贺 丹; 宋英明; 邹树梁; 徐守龙; 王晓冬; 朱志超; 谭桢干; 何志锋; 王新林

doi:10.11889/j.0253-3219.2015.hjs.38.090604

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基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计

核能科学与工程 | 更新时间：2021-03-03

- 基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计
- Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source
- 核技术 2015年38卷第9期文章编号：090604
- 作者机构：
  
  1. 核设施应急安全作业技术与装备湖南省重点实验室,衡阳,421001
  2. 南华大学核科学技术学院,衡阳,421001
  3. 南华大学电气工程学院,衡阳,421001
- 作者简介：
  
  [ "通讯作者: 邹树梁，E-mail: zousl2013@126.com E-mail:hedanyiyi910818@163.com" ]
- 基金信息：
- DOI：10.11889/j.0253-3219.2015.hjs.38.090604
  中图分类号：
- 纸质出版日期：2015-09-10
- 稿件说明：
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贺丹, 宋英明, 邹树梁, 等. 基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计[J]. 核技术, 2015,38(9):090604

HE Dan, SONG Yingming, ZOU Shuliang, et al. Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source [J]. Nuclear techniques, 2015, 38(9): 090604
贺丹, 宋英明, 邹树梁, 等. 基于252Cf源的反应堆结构屏蔽材料屏蔽性能测试装置设计[J]. 核技术, 2015,38(9):090604 DOI： 10.11889/j.0253-3219.2015.hjs.38.090604.

HE Dan, SONG Yingming, ZOU Shuliang, et al. Design of shielding-performance testing-device for reactors construction shielding-material based on 252Cf source [J]. Nuclear techniques, 2015, 38(9): 090604 DOI： 10.11889/j.0253-3219.2015.hjs.38.090604.

摘要

基于252Cf中子源，构建了反应堆结构屏蔽材料屏蔽性能测试装置设计模型。采用MCNP程序建立了测试模型，并逐次模拟计算屏蔽性能测试装置慢化层、中子防护层、γ光子防护层厚度。对于关键的慢化层，采用Geant4程序进一步验证MCNP程序的计算结果。通过分析模拟计算获得了最优屏蔽材料及厚度分别为：慢化层材料为石蜡，厚度为8 cm；中子防护层材料为聚乙烯，厚度为38 cm；γ防护层材料为铁，厚度为11 cm。模拟实验结果表明，所设计屏蔽性能测试装置能够满足中子慢化以及中子、光子防护的需要。

Abstract

Background: New material for the reactor shielding structure is one type of cast-steel impurity doping actinide elements have been adopted. The design parameters of the shielding performance testing device for the various parts of reactor can be obtained by Monte Carlo method. Purpose: This study aims to test the shielding performance of the shielding material of reactor. Methods: First of all

the testing device model was built based on a 252Cf neutron source. Three kinds of models (the thicknesses of the moderation layer

the protective layers of the neutron and gamma ray) are calculated respectively using the MCNP program for the shielding performance testing device. The GEANT4 program was used for the key moderation layer to verify the results obtained by the MCNP program. Results: Through the analysis of simulation results

we obtained optimal shielding materials and the thicknesses of material layer: moderator layer material is paraffin wax

which having a thickness of 8 cm

neutron shielding material is polyethylene

which having a thickness of 38 cm

and γ protective layer material is iron

which having a thickness of 11 cm. Conclusion: Simulation results show that the proposed shielding performance testing device can meet the requirements of neutron moderator

neutron protection and photon protection. Abstract

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