低、中放固体废物处置设施的屏蔽计算

辐射防护通讯 ›› 2016, Vol. 36 ›› Issue (6): 11-15.

低、中放固体废物处置设施的屏蔽计算

谢占军

中核第四研究设计工程有限公司, 石家庄, 050021

收稿日期:2016-08-24 出版日期:2016-12-20 发布日期:2021-11-19
作者简介:谢占军(1983- ),男, 2005年毕业于唐山师范学院物理学专业,学士; 2008年毕业于广西大学理论物理专业,硕士; 工程师。

Shielding Calculation for Low-and-intermediate Level Radioactive Waste Disposal Facilities

Xie Zhanjun

The Fourth Research and Design Engineering Corporation of CNNC, Shijiazhuang,050021

Received:2016-08-24 Online:2016-12-20 Published:2021-11-19

摘要/Abstract

摘要： 天然屏障和工程屏障相结合的多重屏障设计是近地表低、中放固体废物处置场设计的基本原则。本文从辐射防护角度出发,对某低中放固体废物处置场处置单元的设计进行论证。分别采用点核积分法程序QAD和蒙特卡罗法程序MCNP,对处置单元格不同厚度墙体外的剂量率水平进行计算,确定出合理的处置单元构筑物墙体厚度,并得出两种屏蔽计算方法的适用范围。

关键词: 低、中放废物处置, 处置单元, 屏蔽, QAD, MCNP

Abstract: For the design of near surface low-and-intermediate level radioactive waste repository, the principle of multi barriers, which considering both natural and engineered barriers, should be held. From the point of view of radioprotection, the design of a low-and-intermediate level radioactive waste disposal unit is demonstrated. Point kernel integration method QAD and Monte Carlo method MCNP were used to calculate the dose rate outside the walls with different thickness of disposal unit. Based on the calculation, the proper thickness of disposal unit wall was decided, and the application scope of each method was worked out.

Key words: Low-and-intermediate level radioactive waste disposal, Disposal unit, Shielding, QAD, MCNP

中图分类号:

TL75

谢占军. 低、中放固体废物处置设施的屏蔽计算[J]. 辐射防护通讯, 2016, 36(6): 11-15.

Xie Zhanjun. Shielding Calculation for Low-and-intermediate Level Radioactive Waste Disposal Facilities[J]. RADIATION PROTECTION BULLETIN, 2016, 36(6): 11-15.

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