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241Am-Be中子参考辐射的蒙特卡罗模拟研究

张颂 魏彪 刘易鑫 毛本将 钱易坤 黄宇晨 冯鹏

张颂, 魏彪, 刘易鑫, 等. 241Am-Be中子参考辐射的蒙特卡罗模拟研究[J]. 强激光与粒子束, 2020, 32: 056001. doi: 10.11884/HPLPB202032.190478
引用本文: 张颂, 魏彪, 刘易鑫, 等. 241Am-Be中子参考辐射的蒙特卡罗模拟研究[J]. 强激光与粒子束, 2020, 32: 056001. doi: 10.11884/HPLPB202032.190478
Zhang Song, Wei Biao, Liu Yixin, et al. Monte Carlo simulation research on reference neutron radiation of 241Am-Be radionuclide[J]. High Power Laser and Particle Beams, 2020, 32: 056001. doi: 10.11884/HPLPB202032.190478
Citation: Zhang Song, Wei Biao, Liu Yixin, et al. Monte Carlo simulation research on reference neutron radiation of 241Am-Be radionuclide[J]. High Power Laser and Particle Beams, 2020, 32: 056001. doi: 10.11884/HPLPB202032.190478

241Am-Be中子参考辐射的蒙特卡罗模拟研究

doi: 10.11884/HPLPB202032.190478
基金项目: 中央高校基本科研业务费国防创新专项(2018CDGFGD0008);国家自然科学基金青年基金项目(11805111)
详细信息
    作者简介:

    张 颂(1995—),男,硕士研究生,从事电离辐射剂量学研究;zhangsong372@126.com

    通讯作者:

    冯 鹏(1981—),男,博士,副教授,从事核信号检测技术及其应用研究;coe-fp@cqu.edu.cn

  • 中图分类号: TL72

Monte Carlo simulation research on reference neutron radiation of 241Am-Be radionuclide

  • 摘要:

    研究用于校准场所中子剂量监测仪表的241Am-Be中子参考辐射场计量特性。采用蒙特卡罗方法模拟了空气自由中子参考辐射(FRNR),GB/T 14055规定的最小尺寸中子参考辐射(SRNR)和实际中子参考辐射(ARNR)中不同检验点处中子周围剂量当量率、散射中子占比和能谱分布特征。研究结果表明,空气对FRNR中的剂量率和能谱分布影响小,近似为理想中子参考辐射;采用5%含硼聚乙烯作屏蔽的最小尺寸SRNR可减少热中子,降低散射中子占比,影锥法不适用于小尺寸中子参考辐射中对散射中子的修正;ARNR中的散射中子更少、占比更低,影锥法所得散射中子占比与理论值基本一致。

  • 图  1  241Am-Be中子源能谱

    Figure  1.  Neutron energy spectrum of a 241Am-Be source

    图  2  SRNR模型

    Figure  2.  SRNR models

    图  3  影锥模型

    Figure  3.  Model of shadow cone

    图  4  不同条件下FRNR中各检验点中子能谱分布

    Figure  4.  Neutron energy spectrum distribution at each point of test under different FRNR

    图  5  SRNR中各检验点剂量率

    (A:polyethylene containing 5% boron,B:concrete;solid line:half-cubical type,dotted line:cubical type)

    Figure  5.  Dose rate of each point of test under SRNR

    图  6  半立方体SRNR中各检验点中子能谱分布

    Figure  6.  Neutron energy spectrum distribution at each point of test under half-cubical type SRNR

    图  7  三种中子参考辐射中各检验点剂量率(屏蔽材料:混凝土)

    Figure  7.  Dose rate of each point of test under three kinds of reference neutron radiation (shielding material:concrete)

    图  8  三种中子参考辐射中0.75 m处检验点中子能谱分布(屏蔽材料:混凝土)

    Figure  8.  Neutron energy spectrum distribution at 0.75 m point of test under three kinds of reference neutron radiation (shielding material:concrete)

    表  1  FRNR和空气FRNR中各检验点剂量率、空气散射贡献占比

    Table  1.   The dose rate of each point of test and the contribution proportion of air scattering in FRNR and air FRNR

    distance/mdose rate/(μSv·h−1)④the contribution proportion of
    air scattering obtained by
    shadow-cone method(③/①)/%
    ⑤the theoretical contribution
    proportion of air
    scattering[(②—①)/①]/%
    ①FRNR②FRNR+air③FRNR+air+
    shadow cone
    0.7552.0152.240.701.350.44
    0.8540.4940.690.521.280.49
    0.9532.4232.590.421.300.52
    1.0526.5326.690.361.360.60
    1.1522.1222.260.321.450.63
    1.2518.7218.850.281.500.69
    1.3516.0516.170.251.560.75
    下载: 导出CSV

    表  2  SRNR中各检验点散射中子剂量率贡献占比(影锥法)

    Table  2.   The contribution proportion of scattered neutron dose rate at each point of test under SRNR (shadow-cone method)

    typecontribution proportion at different distance/%
    0.75 m0.85 m0.95 m1.05 m1.15 m1.25 m1.35 m
    A18.2910.0311.9314.0016.1618.4220.77
    A28.5610.7313.1915.8918.7021.3322.90
    B117.1121.2725.8030.7035.9441.5247.57
    B218.6223.8929.7736.2343.1650.1855.99
    Notes:A—polyethylene containing 5% boron,B—concrete;1—half-cubical type,2—cubical type
    下载: 导出CSV

    表  3  SRNR中各检验点散射中子剂量率贡献占比(理论值)

    Table  3.   The contribution proportion of scattered neutron dose rate at each point of test under SRNR (theoretical value)

    typecontribution proportion at different distance/%
    0.75 m0.85 m0.95 m1.05 m1.15 m1.25 m1.35 m
    A17.529.3511.3213.3915.5917.9120.37
    A28.0910.3813.0216.0219.4523.3627.85
    B116.5920.8125.3730.3235.6441.3547.45
    B218.7024.0530.2137.2445.3454.7265.89
    Notes:A—polyethylene containing 5% boron,B—concrete;1—half-cubical type,2—cubical type
    下载: 导出CSV

    表  4  三种中子参考辐射中各检验点散射中子剂量率贡献占比(屏蔽材料:混凝土)

    Table  4.   The contribution proportion of scattered neutron dose rate at each point of test under three kinds of reference neutron radiation (shielding material:concrete)

    typecontribution proportion at different distance/%
    0.75 m0.85 m0.95 m1.05 m1.15 m1.25 m1.35 m
    FRNR+airshadow-cone method1.351.281.301.361.451.501.56
    ARNRshadow-cone method10.9713.6516.5719.6922.9926.4630.07
    SRNR(1)shadow-cone method17.1121.2725.8030.7035.9441.5247.57
    SRNR(2)shadow-cone method18.6223.8929.7736.2343.1650.1855.99
    FRNR+airtheoretical value0.440.490.520.600.630.690.75
    ARNRtheoretical value10.4813.1216.0119.0722.3625.7629.37
    SRNR(1)theoretical value16.5920.8125.3730.3235.6441.3547.45
    SRNR(2)theoretical value18.7024.0530.2137.2445.3454.7265.89
    Notes:1—half-cubical type,2—cubical type
    下载: 导出CSV
  • [1] 杨元第, 李德红. 电离辐射计量发展概况[C]//辐射防护分会2012年学术年会论文集. 2012: 17-20.

    Yang Yuandi, Li Dehong. Development of ionizing radiation measurement[C]//Proceedings of the 2012 Annual Conference of the Radiation Protection Branch. 2012: 17-20
    [2] 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. (Zhang Hui, Fan Cheng, Gong Xiaoming. The device of the neutron reference radiation with radionuclide neutron sources[J]. Acta Metrologica Sinica, 2011, 32(6): 559-563 doi: 10.3969/j.issn.1000-1158.2011.06.17
    [3] Yun H K, Hyeonseo P, Yong K K, et al. Reference thermal neutron field at KRISS for calibration of neutron detectors[J]. Radiation Measurement, 2017, 107: 3-79.
    [4] Dreyzin V E, Grimov A A, Logvinov D I. Creating reference neutron fields for calibration of neutron spectrometers and computing their spectra[J]. Journal of Applied Spectroscopy, 2018, 85(4): 680-685. doi: 10.1007/s10812-018-0704-7
    [5] JJG 852-2006, 中华人民共和国国家计量检定规程中子周围计量当量(率)仪[S].

    JJG 852-2006, People’s Republic of China national verification procedures: Neutron ambient dose equivalent(rate) meters[S]
    [6] David T, Roberto B, Roberto M, et al. Revision of ISO 8529—reference neutron radiations[J]. Radiation Protection Dosimetry, 2018, 180(1/4): 21-24.
    [7] 李景云. 参考中子辐射与辐射防护中子测量装置校准[J]. 辐射防护通讯, 2003, 23(6):8-23. (Li Jingyun. Reference neutron radiation and calibration of measuring device for radiation protection purpose[J]. Radiation Protection Bulletin, 2003, 23(6): 8-23 doi: 10.3969/j.issn.1004-6356.2003.06.002
    [8] 骆海龙, 刘毅娜, 王志强, 等. 中子剂量仪表校准的本底扣除方法研究[J]. 辐射防护, 2012, 32(5):273-276. (Luo Hailong, Liu Yina, Wang Zhiqiang, et al. Comparison of response with different background subtracting methods in neutron dosemeter calibration[J]. Radiation Protection, 2012, 32(5): 273-276
    [9] Komar D, Kutsen S. Influence of scattered neutron radiation on metrological characteristics of AT140 neutron calibration facility[J]. Devices and Methods Measurements, 2017, 8(1): 23-31.
    [10] 霍雷, 刘剑利, 马永和. 辐射剂量与防护[M]. 北京: 电子工业出版社, 2015: 139.

    Huo Lei, Liu Jianli, Ma Yonghe. Radiation dose and protection[M]. Beijing: Publishing House of Electronics Industry, 2015: 139
    [11] GB/T 14055.1-2008, 中子参考辐射第1部分: 辐射特性和产生方法[S].

    GB/T 14055.1-2008, Reference neutron radiations—Part 1: Characteristics and methods of production[S]
    [12] ISO 8529-1: 2001(E), Reference neutron radiations—Part 1: Characteristics and methods of production[S].
    [13] GB/T 14055.2-2012, 中子参考辐射第2部分: 与表征辐射场基本量相关的辐射防护仪表校准基础[S].

    GB/T 14055.2-2012, Reference neutron radiations—Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field[S]
    [14] ISO 8529-2: 2000(E), Reference neutron radiations—Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field[S].
    [15] 刘毅娜, 王志强, 徐科, 等. 亚太地区中子周围剂量当量(率)仪的校准比对[J]. 原子能科学技术, 2016, 50(1):181-187. (Liu Yina, Wang Zhiqiang, Xu Ke, et al. APMP key comparison for calibration of neutron ambient dose equivalent meter[J]. Atomic Energy Science and Technology, 2016, 50(1): 181-187 doi: 10.7538/yzk.2016.50.01.0181
    [16] Pereira W W, Estrada J J S, Patrao K C S, et al. 241Am-Be(α, n) characterization for a new laboratory facility in Brazil[J]. Radiation Protection Dosimetry, 2018, 180(1/4): 29-32.
    [17] 文德智, 雷家荣, 卓仁鸿, 等. 用于中子剂量当量仪校准的同位素中子参考辐射的建立[J]. 中国核科技报告, 2005(1):119-127. (Wen Dezhi, Lei Jiarong, Zhuo Renhong, et al. The establishment of a radionuclide neutron reference radiations for calibrating neutron dose equivalent devices[J]. China Nuclear Science and Technology Report, 2005(1): 119-127
    [18] The International Commission on Radiation Protection. Conversion coefficients for use in radiological protection against external radiation[R]. ICRP Publication 74, 1996: 200.
    [19] 陈飞达, 唐晓斌, 王鹏, 等. 基于蒙特卡罗方法的中子屏蔽材料设计[J]. 强激光与粒子束, 2012, 24(12):3006-3010. (Chen Feida, Tang Xiaobin, Wang Peng, et al. Neutron shielding material design based on Monte Carlo simulation[J]. High Power Laser and Particle Beams, 2012, 24(12): 3006-3010 doi: 10.3788/HPLPB20122412.3006
    [20] Campo X, Mendez R, Lacerda M A S, et al. Experimental evaluation of neutron shielding materials[J]. Radiation Protection Dosimetry, 2018(1/4): 382-385.
    [21] 周红召, 刘海侠, 李坚, 等. 中子剂量校准实验室室散射影响因素的蒙卡仿真研究[C]//第十七届全国核电子学与核探测技术学术年会论文集. 2014: 592-59.

    Zhou Hongzhao, Liu Haixia, Li Jian, et al. Monte Carlo simulation of factors influencing room-return in neutron calibration laboratory[C]//Proceedings of the 17th National Conference on Nuclear Electronics and Nuclear Detection Technology. 2014: 592-59
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  • 收稿日期:  2019-12-22
  • 修回日期:  2020-02-19
  • 刊出日期:  2020-02-10

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