某高校放射源库辐射场的MCNP模拟及分析

闫学文; 薛向明; 杨雪; 马跃峰

doi:10.11889/j.1000-3436.2018.rrj.36.020601

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某高校放射源库辐射场的MCNP模拟及分析

辐射防护 | 更新时间：2021-12-10

- 某高校放射源库辐射场的MCNP模拟及分析
- MCNP simulation and analysis of radiation fields in radioactive source storehouses in a certain university
- 辐射研究与辐射工艺学报 2018年36卷第2期
- 作者机构：
  
  1.中国辐射防护研究院太原 030006
- 作者简介：
  
  [ "闫学文, 男, 1990年12月出生, 2017年于兰州大学获工学硕士学位, 核技术及应用专业, 目前从事放射卫生学研究工作, 研究实习员, E-mail:540150481@qq.com", "YAN Xuewen (male) was born in December 1990, and received his master’s degree of engineering in Lanzhou University in 2017, majoring in nuclear technology and application. Now he engages in the research work of radiation hygiene as a research intern, E-mail: 540150481@qq.com" ]
- 基金信息：
- DOI：10.11889/j.1000-3436.2018.rrj.36.020601
  中图分类号：
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闫学文, 薛向明, 杨雪, 等. 某高校放射源库辐射场的MCNP模拟及分析[J]. 辐射研究与辐射工艺学报, 2018,36(2):020601-6.

Xuewen YAN, Xiangming XUE, Xue YANG, et al. MCNP simulation and analysis of radiation fields in radioactive source storehouses in a certain university[J]. Journal of Radiation Research and Radiation Processing, 2018,36(2):020601-6.
闫学文, 薛向明, 杨雪, 等. 某高校放射源库辐射场的MCNP模拟及分析[J]. 辐射研究与辐射工艺学报, 2018,36(2):020601-6. DOI： 10.11889/j.1000-3436.2018.rrj.36.020601.

Xuewen YAN, Xiangming XUE, Xue YANG, et al. MCNP simulation and analysis of radiation fields in radioactive source storehouses in a certain university[J]. Journal of Radiation Research and Radiation Processing, 2018,36(2):020601-6. DOI： 10.11889/j.1000-3436.2018.rrj.36.020601.

摘要

采用非现场检测方法，给出某高校放射源库的辐射场分布，并计算出该放射源库的最大存储量，提出防护优化建议。利用MCNP（Monte Carlo N particle transport code）程序模拟计算放射源库辐射场分布，并与实测值对比，验证模拟值的可靠性。结果表明，MCNP程序模拟结果与现场实测值的误差基本保持在10%，能给出较精确的辐射场分布及源库最大存储量。结果提示：利用MCNP程序模拟放射源库及其周围辐射场，能在不进入辐射场的情况下，有效获取任意点处的剂量率；该高校放射源库采取的防护措施能保证在任意关注点处剂量率均小于国家标准限值；对于,137,Cs的最大存储能力为4.88×10,13,Bq，对于,60,Co的最大存储能力为9.99×10,10,Bq。

Abstract

This study was to estimate the radiation field distribution and maximum storage capacity of a certain university's storehouse of radioactive sources without on-site detection, to provide optimized suggestions for radiation protection. The radiation field of the university's storehouse was simulated using Monte Carlo N particle transport code (MCNP) simulations, and compared with experimental values to verify the reliability of the simulation. The results revealed a difference of approximately 10% between the MCNP-simulated and experimentally measured values. Thus, our simulations were observed to provide relatively accurate estimations of the radiation field distribution and maximum storage capacities. The advantage of using MCNP simulations to estimate the radiation field in storehouses of radioactive sources and their surroundings lies in the fact that they enable one to effectively obtain the dose distribution at any point without entering the radiation field. The protective measures taken by our university ensure that the dose rate is less than the standard permissible limit at any point of concern. The maximum storage capacities for ,137,Cs and ,60,Co are estimated to be 4.88×10,13, Bq and 9.99×10,10, Bq, respectively.

关键词

放射源库辐射场源库最大存储量MCNP程序

Keywords

Radioactive sources storehouseRadiation fieldMaximum storage capacity of the radioactive sources storehouseMCNP

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