期刊文献+

快中子堆n,γ混合场中γ光子注量的测量研究 被引量:3

Investigations of the photon fluences in various n+γ mixed fields in the fast neutron reactor
原文传递
导出
摘要 用热释光探测器对快堆堆外n ,γ混合场进行了区分测量 ,结果表明 :该方法可有效的检测出n ,γ混合场的γ成分 ;为了更较精确地测量快堆n ,γ混合场γ光子注量 ,提出了采用新配方的热释光探测器LiFTLD(6 LiF ,7LiF各占5 0 % )与6 LiFTLD成对使用的方法 .考虑到LiFTLD对中子吸收剂量的响应存在LET效应 ,对LiF(Mg ,Cu ,P)TLD进行了中子响应的LET效应因子RLET的实验测定 (RLET≈ 0 0 5 ) ,在此基础上 ,对6 LiF 7LiFTLD的成对使用测量快中子堆的n ,γ混合场中光子注量的方法进行了实验研究 .实验结果表明 ,混合场中的中子在7LiF(Mg ,Cu ,P)中产生的热释光量 (TL)占n ,γ产生的总TL的 8 1%— 17 1% .实验结果表明该方法是行之有效的 .为钝化中子谱的不确定性所致的影响 ,进一步提高γ光子注量测量结果的精度 ,提出了采用新配方的LiFTLD(6 LiF ,7LiF各占 5 0 % )与6 LiFTLD成对使用测量快堆n ,γ混合场γ光子注量的方法 . The LET factors R LET ( R LET ≈0 05) of neutron response for LiF(Mg,Cu,P)TLD have been determined experimentally due to the existing LET effects of the response for LiFTLD to neutron absorbed dose.Based on the data,one experimental method to define the photon fluence in various n+γ mixed fields in the fast neutron reactor with coupled 6LiF 7LiFTL detectors has been checked.The experimental results show that the ratios of the TL due to the effect of neutrons in 7LiF(Mg,Cu,P)to the total TL due to the combined effects of the γ rays and neutrons are between 8 1% and 17.1%.In order to reduce the effect caused by the uncertainty of the neutron spectra and improve the accuracy of the measurement for the photon fluence,we propose a new LiFTLD,in which there are 50% 6LiF and 50% 7LiF.It is coupled with a 6LiFTLD to measure the photon fluence in the n+γ mixed fields.
出处 《物理学报》 SCIE EI CAS CSCD 北大核心 2003年第1期53-57,共5页 Acta Physica Sinica
基金 中国工程物理研究院行业科技预研基金 (批准号 :2 0 0 10 2 0 9)资助的课题~~
关键词 快中子堆 测量 n γ混合场 吸收剂量 LiFTLD LET 热释光探测器 γ光子流量 mixed neutron gamma field, absorbed dose, LiFTLD, LET
  • 相关文献

参考文献6

  • 1[1]Frank H Attix and Tochilin E 1969 Radiation Dosimetry (New York and London:Acadimic Press)p323
  • 2[2]Li Z Y,Wang C S and Chem D 1987 Radiation Protection 7 47
  • 3[3]Simons G G and Yule T T 1979 Nuclear Science and Engineering 53 162
  • 4[4]Horowitz Y S and Shacher B B 1988 Radiation Protection Dosimetry 23 401
  • 5[5]Lei J R,Zhao M Zh,Zhao Letal 2001 Atomic Energy Science and Technoloyg 4 367
  • 6[6]Shou-Ichi Tanaka Yutaka 1974 Nucl.Instrum.Method 117 93

同被引文献39

  • 1王兴功,骆亿生,张红,周郁,郭勇.CR-39固体核径迹探测器用于中子测量化学蚀刻参数的优化[J].核技术,2005,28(4):319-323. 被引量:8
  • 2Noltet R, Behrent R. Radiation Protection Dosimetry,1999, 84(1-4): 367-379
  • 3Briesmeister J F. MCNP-A General Monte Carlo N-Particle Transport Code: LA-12625-M. US: Los Alamos National Laboratory, 1997
  • 4Shtejer-Diaz K et al. Applied Radiation and Isotopes, 2003,59:263-266
  • 5Rodriguez M L. Health Physics, 2003, 85(4): 433-437
  • 6Matzke M. Unfolding of Pulse Height Spectra: The HEPRO Program System: PTB-N-19. Braunschweig:Physikalisch Technische Bundesanstalt, 1994
  • 7Reginatto M, Goldhagen P. A Computer Code for the Deconvolution of Multisphere Neutron Spectrometer Data Using the Maximum Entropy Method: EML-595. New York:Environmental Measurements Laboratory, 1998
  • 8McElroy W N et al. A Computer-Automated Iterative Method for Neutron Flux Spectra Determination by Foil Activation: AFWL-TR-67-41. U S: Air Force Weapons Laboratory, 1967
  • 9Robertson M E A. Identification and Reduction of Errors in Thermoluminescence Dosimetry System. England: D.A.Pitman Ltd. Weybridge, Surrey, 1981. 6
  • 10Ipe N E, Liu J C, Buddemeier B R, et al. A comparison of the neutron response of CR-39 made by different manufacturers[J]. Radiation Protection Dosimetry, 1992, 44(1-4), 317-321.

引证文献3

二级引证文献8

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部