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^(252)Cf(D_2O)中子源实验室中子散射的模拟及验证 被引量:2

Simulation and verification of neutron scattering at ^(252)Cf(D_2O) neutron laboratory
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摘要 为了准确刻度中子剂量当量仪的性能参数以及验证中子剂量当量仪设计的准确性,在252Cf(D2O)源实验室进行实验校准之前,先采用MCNP5分别模拟分析实验室中空气、墙壁以及石蜡桶对探头中子计数的影响。模拟实验表明,在理想条件下,随着源与探头距离的增大,中子计数率越来越小;空气对中子计数的影响呈先增加后减小再增加的趋势,中子散射率不超过10%,且距离越近,空气散射的中子对探头计数的影响越小;当探头与源距离260cm左右时,石蜡桶对探头计数的影响最小,达到1%;墙壁对中子计数的影响随着探头与源距离增大而逐渐增大,当探头与源距离为360cm时,墙壁散射的中子是源中子计数的2倍;当源与探头距离为175cm时,空气、墙壁以及石蜡桶对源中子的散射最小,测量数据最精确。并通过实验与模拟数据对比表明,源与探头距离在125–300cm之间,计数率误差不超过30%,符合中子剂量测量的技术要求,从而验证了此中子剂量当量仪设计的准确性。 Background: Although the measurement of neutron dose equivalent was initiated several decades ago, the accuracy of the measurement is not high enough due to the dosimeter's sensitivity and fiuence response. Purpose: The aim of this work is to accurately scale the performance parameters and insure the design accuracy of neutron dose equivalent instrument. Methods: MCNP5 was used for simulation analysis of the impact of air, walls, and paraffin in the laboratory respectively on the barrels of neutron counting before experiment. Results: The experimental results show that under ideal conditions, the neutron counting rate decreased with the increase of distance between the source and probe. The air impact on neutron count was up at first and then became weakened, but tended to be strengthened again finally. The neutron scattering rate was less than 10%. And the shorter the distance was, the weaker became air scattering neutrons impact on probe counting. When the probe and the source distance reached 260 cm, the influence of the paraffin barrels was the weakest, which was 1%. The influence of the wall on the neutron count increased with the source-probe distance. When the probe and the source distance was 360 cm, the neutron scattering from the wall was 2 times of that from the source. When the source and the probe distance was 175 cm, all of influences to the neutron scattering reached the minimum, and the measurement data tended to be the most accurate. Conclusion: Through the comparison between experimental and theoretical data, the error of the count rate is less than 30% when the source and the probe distance is between 125-300 cm, confirming with the requirements of the neutron dose measurement technology, which verifies the accuracy of the neutron dose equivalent instrument design.
出处 《核技术》 CAS CSCD 北大核心 2014年第6期29-33,共5页 Nuclear Techniques
基金 国家磁约束核聚变能研究专项(No.2011GB111001) 四川省科技支撑计划项目(No.2009GZ0232)资助
关键词 性能参数 MCNP5 散射中子 剂量当量 Performance parameter, MCNP5, Scattering neutrons, Dose equivalent
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参考文献8

  • 1李安利,王效忠,白希祥,柳卫平,袁媛.用^(252)Cf自发裂变中子源刻度中子探测器效率[J].原子能科学技术,1994,28(2):133-139. 被引量:4
  • 2Cub J,Finckh E,Gebhardt K,et al.The neutron detection efficiency of NE213 detectors measured by means of ^252Cf source[J].Nuclear Instruments and Methods in Physics Research,1989,A274:217-221.
  • 3Smith A,Guenther P,Sjoblom R.Note on the experimental determination of the relative fast-neutron sensitivity of a hydrogenous scintillator[J].Nuclear Instruments and Methods in Physics Research,1977,140:397-400.
  • 4Baba M,Wakabayashi H,lshikawa M,et al.Fission spectrum measurement of ^232Th and ^238U for 2 MeV neutrons[R].IAEA-INDC(NDS)-220,1989:149.
  • 5田时海,卢艳,王和义,陈旭,袁永刚.中子剂量当量仪的设计[J].核技术,2012,35(9):665-669. 被引量:2
  • 6Rimpler A.Dose equivalent response of neutron surver meters for several neutron fields[J].Radiation Protection Dosimetry,1992,44(1-4):189-192.
  • 7Wiegel B,Alevra A V,Siebert B R L.Calculations of the response functions of bonnet spheres with a spherical 3He proportional counter using a realistic detector model:PTB-N-21[R].Braunschweig Germany,Physikalisch-Technische-Bundesanstalt,1994.
  • 8陈常茂,谭民,陈勤,等.可携式中子剂量当量率仪[J].辐射防护,1990,10(2):108-112.

二级参考文献11

  • 1魏迎光,刘森林,孙莉峰,王彦锋.一种高灵敏度环境中子剂量当量仪的能量响应计算与实验验证[J].核技术,2007,30(4):376-380. 被引量:3
  • 2ICRP. Conversion coefficients for use in radiological protection against external radiation. ICRP Publication 74. Pergamon Press, 1966.
  • 3ISO. Neutron reference radiation for calibrating neutron- measuring devices used for radiation protection purposes and for determining their response as function of neutron energy [P]. ISO 8529, 1989.
  • 4Wiegel B, Alevra A V, Siehert B R L. Calculations of the response functions of Bonner spherical 3He proportional counter using a realistic detector model. PTB-Bericht N-21, 1994.
  • 5MCNP4A. Monte Carlo N-particle transport code system. Los Alamos National Laboratory, Los Alamos, New Mexico, 1993.
  • 6ISO8529-3 (1989), Neutron Reference Radiation Part 3 Calibration of Area and Personal Dosimeters and Determination of Response as a Function of Energy and Angle of Incidence[S].
  • 7ISO 1993 (E), Guide to Expression of Uncertainty in Measurement [S].
  • 8Matzke M. Propagation of Uncertainties in Unfolding Procedures: PTB2S7201[R]. Braunschweig, Germany: Physikalisch Technische Bundesanstalt, 1994.
  • 9Mourgues M, Carossi J C, Portal G. A light rem-counter oJ advanced technology. Neutron dosimetry, Proc Eurtom 5e Symp, 1989, 27(2): 103.
  • 10孟江辰,黄胜年.^(252)Cf微型快裂变室[J].核电子学与探测技术,1989,9(1):1-6. 被引量:5

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