基于镅铍中子源的简易照射装置及其剂量学特性研究

doi:10.13491/j.issn.1004-714X.2021.02.010

2021, Vol. 30

Issue (2): 168-172 DOI: 10.13491/j.issn.1004-714X.2021.02.010

Radiation Monitoring/Original Articles

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Study on the radiation device of ²⁴¹Am-Be neutron source and its dosimetric properties

TANG Xiaohao¹, HONG Bo², FAN Shengnan³, CAO Lei⁴, LAN Changlin², PAN Xiaodong²

1. Editorial Department of 《Atomic Energy Science and Technology》, China Institute of Atomic Energy, Beijing 102413 China;
2. School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000 China;
3. National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088 China;
4. The Beijing Prevention and Treatment Hospital of Occupational Disease for Chemical Industry, Beijing 100089 China

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Abstract Objective To design and build a set of experimental equipment for neutron radiation irradiation by using the ²⁴¹Am-Be neutron source.Methods In the preliminary work, the spatial distribution data of the neutron energy spectrum and the gamma energy spectrum inside and outside the device were simulated by Monte Carlo method, and the changes of radiation fluence rate with spatial distribution was studied. The model of the ²⁴¹Am-Be neutron device was established, and the neutron transport process in the irradiation field was studied using the method of shadow cone, inverse square law and other data analysis methods.Results Based on the simulation results, the normalized effective does of fast neutron fluence at the measurement point is about 72.9 pSv/n, and the one of photon fluence is about 3.04 pSv/γ. The ratio of effective dose of photon fluence to neuteon is about 4.17%.Conclusion Using Monte Carlo method, a standard model of ²⁴¹Am-Be neutron source was constructed, the shadow cone design was optimized, and the feasibility of using the shadow cone conversion method to establish a standard neutron source radiation device was discussed.

Key words： ²⁴¹Am-Be Neutron Source Monte Carlo Calculation Shadow Cone Method

Received: 11 September 2020

PACS:

R144.1

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	TANG Xiaohao
	HONG Bo
	FAN Shengnan
	CAO Lei
	LAN Changlin
	PAN Xiaodong

Cite this article:

TANG Xiaohao,HONG Bo,FAN Shengnan, et al. Study on the radiation device of ²⁴¹Am-Be neutron source and its dosimetric properties[J]. , 2021, 30(2): 168-172.

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http://www.zgfsws.com/EN/10.13491/j.issn.1004-714X.2021.02.010 OR http://www.zgfsws.com/EN/Y2021/V30/I2/168

[1] ISO 8529-2: 2000. Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field[S].
[2] 谢菊英, 马慧, 程品晶. 高活度中子源的辐射防护安全思路[J]. 中国辐射卫生,2012,21(2):212-214. DOI: 10.13491/j.cnki.issn.1004-714X.2012.02.020
Xie JY, Ma H, Cheng PJ. Radiation protection of high activity neutron source[J]. Chin J Radiol Health, 2012, 21(2): 212-214. DOI: 10.13491/j.cnki.issn.1004-714X.2012.02.020
[3] 张辉, 樊成, 龚晓明. 采用放射性核素中子源的中子参考辐射装置[J]. 计量学报,2011,32(6):559-563. DOI: 10.3969/j.issn.1000-1158.2011.06.17
Zhang H, Fan C, Gong XM. The device of the neutron reference radiation with radionuclide neutron sources[J]. Acta Metrol Sin, 2011, 32(6): 559-563. DOI: 10.3969/j.issn.1000-1158.2011.06.17
[4] EC, FAO, IAEA, ILO, OECD/NEA, PHAO, UNEP, WHO. Radiation protection and safety of radiation sources: International basic safety standards(IBSS)[M].Vienna: IAEA, 2014.
[5] 全林, 江新标, 苗亮亮, 等. 镅铍中子源实验装置屏蔽设计[J]. 辐射防护,2013,33(4):220-225
Quan L, Jiang XB, Miao LL, et al. Shielding design for neutron source device of ²⁴¹Am-be[J]. Radiat Prot, 2013, 33(4): 220-225
[6] ISO 8529—1: 2001. Reference neutron radiations - Part 1: Characteristics and methods of production[S].2001.
[7] ICRP116. Conversion coefficients for radiological protection quantities for external radiation exposures[M].2010.
[8] 张京, 丁艳秋, 拓飞, 等. 地表及空勤航线中子辐射水平测量现状[J]. 中国辐射卫生,2017,26(2):217-220. DOI: 10.3969/j.issn.1004-714X.2017.02.029
Zhang J, Ding YQ, Tuo F, et al. Investigation of air ground interface environmental neutron radiation level[J]. Chin J Radiol Health, 2017, 26(2): 217-220. DOI: 10.3969/j.issn.1004-714X.2017.02.029
[9] 潘翔, 林志凯, 潘俊峰. 5%含硼聚乙烯屏蔽快中子的实验研究与分析[J]. 中国辐射卫生,2013,22(4):396-397, 400. DOI: 10.13491/j.cnki.issn.1004-714X.2013.04.001
Pan X, Lin ZK, Pan JF. Experimental studies and analysis of 5% borated polyethylene shielding fast neutron[J]. Chin J Radiol Health, 2013, 22(4): 396-397, 400. DOI: 10.13491/j.cnki.issn.1004-714X.2013.04.001
[10] 国家卫生与计划生育委员会. GBZ/T 244—2017电离辐射所致皮肤剂量的估算方法[S]. 北京: 中国标准出版社, 2017.
National Health and Family Planning Commission of the People's Republic of China. GBZ/T 244—2017. Estimation method of skin dose caused by ionizing radiation[S]. Beijing: Standards Press of China, 2017.
[11] 成杰, 谢向东. 测量血钠活度估算中子照射人体剂量方法与进展[J]. 中国辐射卫生,2011,20(1):118-121. DOI: 10.13491/j.cnki.issn.1004-714x.2011.01.023
Cheng J, Xie XD. Methods and progress of human dose estimation by measuring blood sodium activity[J]. Chin J Radiol Health, 2011, 20(1): 118-121. DOI: 10.13491/j.cnki.issn.1004-714x.2011.01.023