期刊文献+

γ射线穿过UF_6后周围剂量当量累积因子的模拟计算

Monte Carlo Calculation of Buildup Factor for Ambient Dose Equivalent due to Passing of Gamma-ray throuth UF_6
下载PDF
导出
摘要 采用EGS5蒙特卡罗程序计算了γ射线穿过UF6材料后的周围剂量当量累积因子。计算给出了50 keV~3MeV范围,1~10平均自由程下的光子周围剂量当量累积因子,并给出了与计算值符合度较好的参数化拟合公式。计算结果将便于采用线性减弱系数对涉及UF6材料的剂量计算。 In this study, EGS5 Monte Carlo code was used to calculate the buildup factor for ambient dose equivalent due to the passing of gamma-ray through uranium hexafluoride with photon energy range of 50 keV to 3 MeV and depth of 1-10 mean free path. The fitted formulae were also given based on Origin software for cal- culating ambient dose equivalent related to UF6 material. The results from fitted formulae show a good agree- ment with calculated values.
出处 《辐射防护通讯》 2012年第6期19-22,共4页 Radiation Protection Bulletin
关键词 周围剂量当量 累积因子 UF6 Ambient dose equivalent Buildup factor UF6
  • 相关文献

参考文献8

  • 1Sardari D, Saudi S, Tajik M. Evaluation of Gamma Ray Buildup Factor Data in Water with MCNP4C Code [ R]. Annuals of Nuclear Energy 38, 2011:628.
  • 2ICRP. Conversion Coefficients for use in Radiological Pro- tection against Exteral Radiation [ R]. ICRP Publication74, 1996.
  • 3Hirayama H, Namito Y, Bielajew A F, et al. The EGS5 Code System[R]. SLAC-R-730, 2005.
  • 4White G R. The Penetration and Diffusion of 60^ Co Gamma- rays in Water Using Spherical Geometry[ J ]. Physical Re- view, 1950,80:154.
  • 5Oak Ridge National Laboratory. New Gamma-ray Buildup Fator Data for Point Kernel Calculations: ANS-6.4. 3Standard Reference Data[R]. ORNL/RSIC-49, 1988.
  • 6Berger M J, Hubbell J H, Sehzer S M, et al. XCOM: Photon Cross Sections Database [OL]. http://www, nist. gov/pml/data/xcom/index, cfm.
  • 7Lawrence Berkeley National Laboratory[ OL]. X-ray Data Booklet. http ://xdb. lbl. gov.
  • 8OriginLab Corporation. Origin 8 User Guide[ R]. 2007.

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