期刊论文

Zou, S.

中文

核技术

0253-3219

2015

38

9

090604-1-090604-6

10.11889/j.0253-3219.2015.hjs.38.090604

本校为第一机构

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。

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 layer...