期刊文献+

蒙卡-点核耦合方法计算核设施退役辐射场 被引量:3

The Monte Carlo-Point Kernel Coupling Method is used to Calculate the Radiation Field of Nuclear Facilities
下载PDF
导出
摘要 在核设施退役过程中,随着退役设备的拆除,需要计算其三维辐射场的分布,并对核退役场景进行快速、精确的剂量计算和评估,以降低辐射对人员和环境的危害。目前,使用单一的确定论方法和随机性方法计算结构复杂的辐射场均存在不足,无法快速准确的计算退役设施辐射场的分布,而蒙卡-点核耦合计算可精确快速给出辐射场的分布,因此,利用蒙卡-点核耦合方法计算退役辐射场。对多点源辐射场模型计算结果表明,蒙卡-点核耦合计算比单一点核方法计算误差精度提高约1~2个数量级,相比于单一的蒙特卡罗计算可节约几十倍的时间;同时,蒙卡-点核耦合计算对体源模型的计算结果表明,耦合计算比单一的蒙卡方法计算速度提高几十倍,且最大相对误差在30%以内,计算精度较高。基于蒙卡-点核耦合计算方法,初步开发了核设施退役三维辐射场计算程序软件。 In the process of decommissioning of nuclear facilities,with the demolition of retired equipment that need to calculate the distribution of the 3D radiation field,then a rapid and accurate dose calculation and evaluation of the nuclear decommissioning scenario is carried out to reduce the radiation hazard to the personnel and the environment.At present,calculation of radiation fields with complex structure and large scale shielding using the deterministic method and stochastic method single calculation have their drawbacks,and the distribution of radiation fields in decommissioning facilities can not be calculated quickly and accurately,but the distribution of radiation field can be given accurately and rapidly by the calculation of the Monte Carlo-Point Kernel coupling method.Therefor we use Monte Carlo-Point Kernel coupling calculation method for radiation field calculation.Based on this method,the results of calculating multi-point sources radiation field show that Monte Carlo-Point Kernel coupling method is able to increase the accuracy about 1-2 orders of magnitude compared with single point kernel integral method and it could save several times of time compared with traditional Monte Carlo method.At the same time,Monte Carlo-Point Kernel coupling calculation of calculation of the body source model.The results show that the coupling calculation of Monte Carlo method than single calculation speed is increased several times,and the maximum relative error is within30%,highly accuracy.The software of decommissioned 3D radiation field of nuclear facilities is initially developed based on the Monte Carlo-Point Kernel coupling calculation method.
作者 郭亚平 宋英明 卢川 付孟婷 张泽寰 GUO Ya-ping;SONG Ying-ming;LU Chuan;FU Meng-ting;ZHANG Ze-huan(School of Nuclear Science and Technology,University of South China,Hengyang of Hunan Prov.421001,China;China Nuclear Power Research and Design Institute,National Key Laboratory of Nuclear Reactor System Design Technology,Chengdu of Sichuan Prov.610213)
出处 《核科学与工程》 CAS CSCD 北大核心 2018年第6期1002-1007,共6页 Nuclear Science and Engineering
基金 装备预先研究项目(32102040505) 湖南省研究生科研创新项目资助
关键词 辐射场计算 复杂源项 蒙卡-点核耦合计算 Radiation field Calculation Complex sources Monte Carlo-Point Kernel coupling calculation
  • 相关文献

参考文献3

二级参考文献43

  • 1American Nuclear Society. ANSI/ANS-6. 4. 3-- 1991 Gamma-ray attenuation coefficients and build up factors for engineering materials [S]. USA: American Nuclear Society, 1991.
  • 2y射线屏蔽参考手册[M].北京:原子能出版社,1976:95119.
  • 3ASANO Y, SAKAMOTO Y. Gamma-ray build- up factor for heavy concretes[R]. Japan.. Japan Atomic Energy Agency, 2007.
  • 4NELSON W R, HIRAYAMA H, ROGERS D W O. The EGS4 code system[M]. California: Stanford Linear Accelerator Center Stanford Uni- versity, 1985: 1.
  • 5HARIMA Y. A historical review and current status of buildup factor calculations and applica- tions [J]. Radiation Physics and Chemistry, 1993, 41(4/5): 631-672.
  • 6HIRAYAMA H. Calculation of gamma-ray ex- posure buildup factors up to 40 mfp using the EGS4 Monte Carlo code with a particle splitting [J]. Journal of Nuclear Science and Technology, 1995, 32.. 1 201-1 207.
  • 7张雷.蒙卡方法EGS4在7屏蔽积累因子计算中的应用[D].太原:中国辐射防护研究院,2010.
  • 8ALMENAS K, KALIATKA A, USPURAS E. The ignalina source book, ignalina RBMK-1500 [M]. Lithuania: Ignalina Safety Analysis Group Lithuanian Energy Institute, 1998: 51.
  • 9SAKAMOTO Y. Photon cross section data PHOTX for PEGS4 code[C] // Proceeding of the 3rd EGS4 User's Meeting. Japan; KEK Pro- ceedings, 1993: 77-82.
  • 10EISENHAUER C M, SIMMONS G L. Point isotropic gamma-ray buildup factors in concrete[J].Nuclear Science and Engineering, 1975, 56 (3): 263-270.

共引文献7

同被引文献15

引证文献3

二级引证文献1

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