辐射屏蔽专用蒙特卡罗软件RShieldMC开发与验证
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摘要
辐射屏蔽计算是核电厂辐射防护设计和审评的重要内容之一。国际屏蔽计算软件对中国实行"出口封锁",制约了我国核电辐射屏蔽审核计算能力,因此,研发了具有自主知识产权的基于蒙特卡罗方法的辐射屏蔽专用蒙特卡罗软件RShieldMC(Radiation Shielding Monte Carlo)。为了验证RShieldMC程序,进行中子注量率计算的准确性和适用性,利用秦山一期反应堆结构与辐照监督管相关参数,通过RShieldMC可视化前处理模块建立辐照监督管屏蔽计算模型,计算秦山一期反应堆辐照监督管堆芯中平面和上焊缝处的中子注量率。RShieldMC程序计算结果与辐照监督管实验测量值以及MCNP(Monte Carlo N-Particle)、JMCT-S(J Monte Carlo Transport)、TORT(Three-dimensional Neutron/Photon Transport)程序计算结果符合较好,验证了RShieldMC软件在中子注量率计算中的可用性及正确性。
[Background] Radiation shielding calculation is one of the important contents in nuclear power plant radiation protection design and evaluation. The international shield calculation software implements the "export blockade" on China, which limits the calculation ability of radiation shielding audit. [Purpose] This study aims to develop a dedicate radiation shielding software and verify its validity and correctness in neutron flux calculation.[Methods] First of all, based on Monte-Carlo method, a radiation shielding software, named RShieldMC, was developed. Then the measurement data of Qinshan radiation monitoring tube was used for the code verification. The Qinshan No.1 nuclear plant was modeled via visual modeling software of RShieldMC. The neutron flux of the midplane and upper weld in the radiation monitoring tube were calculated by using RShieldMC code. [Results] The calculated results of RShieldMC are in good consistency with the measured values of the radiation monitoring tube test. In addition, the results were also compared with that of MCNP(Monte Carlo N-Particle), JMCT-S(J Monte Carlo transport)and TORT(Three-dimensional Neutron/Photon Transport)programs. [Conclusion] The consistency of the experimental results demonstrates the applicability of RShieldMC in the calculation of neutron flux in PWR.
[Background] Radiation shielding calculation is one of the important contents in nuclear power plant radiation protection design and evaluation. The international shield calculation software implements the "export blockade" on China, which limits the calculation ability of radiation shielding audit. [Purpose] This study aims to develop a dedicate radiation shielding software and verify its validity and correctness in neutron flux calculation.[Methods] First of all, based on Monte-Carlo method, a radiation shielding software, named RShieldMC, was developed. Then the measurement data of Qinshan radiation monitoring tube was used for the code verification. The Qinshan No.1 nuclear plant was modeled via visual modeling software of RShieldMC. The neutron flux of the midplane and upper weld in the radiation monitoring tube were calculated by using RShieldMC code. [Results] The calculated results of RShieldMC are in good consistency with the measured values of the radiation monitoring tube test. In addition, the results were also compared with that of MCNP(Monte Carlo N-Particle), JMCT-S(J Monte Carlo transport)and TORT(Three-dimensional Neutron/Photon Transport)programs. [Conclusion] The consistency of the experimental results demonstrates the applicability of RShieldMC in the calculation of neutron flux in PWR.
引文
1张琳,李文宏,杨红义.福岛核事故后核电厂安全改进行动分析[J].原子能科学技术,2014,48(3):486-491.DOI:10.7538/yzk.2014.48.03.0486.ZHANG Lin,LI Wenhong,YANG Hongyi.Analysis of nuclear power plant safety improvement action after fukushima daiichi NPP accident[J].Atomic Energy Science and Technology,2014,48(3):486-491.DOI:10.7538/yzk.2014.48.03.0486.
2国家核安全局.福岛核事故后核电厂改进行动通用技术要求(试行)[R].北京:国家核安全局,2012.National Nuclear Safety Administration.General technical requirements for nuclear power plant improvement actions after the fukushima accident(trial)[R].Beijing:National Nuclear Safety Administration,2012.
3 European Union.Technical summary on the implementation of comprehensive risk and safety assessments of nuclear power plants in the European Union[R].Brussels:European Commission,2012.DOI:10.1371/journal.ppat.1004184.
4 IAEA.IAEA action plan on nuclear safety[R].Vienna:IAEA,2011.DOI:10.1016/j.esr.2012.11.008.
5 Briesmeister J F MCNP-a general Monte Carlo N-particle transport code[R].Version4C,LA-13709-M.USA:LANL,2000.
6 Rhoades W A,Simpson D B.The TORT threedimensional discrete ordinates neutron/photon transport code[R].ORNL/TM13221.USA:Oak Ridge National Laboratory,1997.
7 Tekin H O,Manici T.Simulations of mass attenuation coefficients for shielding materials using the MCNP-Xcode[J].Nuclear Science and Techniques,2017,28:95.DOI:10.1007/s41365-017-0253-4.
8 Bagheri R,Moghaddam A K,Yousefi A.Gamma-ray shielding study of light to heavyweight concretes using MCNP-4C code[J].Nuclear Science and Techniques,2017,28:15.DOI:10.1007/s41365-016-0167-6.
9 Salimi M,Ghal-Eh N,Amirabadi E A.Characterization of a new shielding rubber for use in neutron-gamma mixed fields[J].Nuclear Science and Techniques,2018,29:36.DOI:10.1007/s41365-018-0371-7.
10 Dong M G,Xue X X,Singh V P,et al.Shielding effectiveness of boron-containing ores in Liaoning province of China against gamma rays and thermal neutrons[J].Nuclear Science and Techniques,2018,29:58.DOI:10.1007/s41365-018-0397-x.
11清华大学.蒙卡软件RShieldMC使用手册[M].A版.2017.Tsinghua University.User manual of Monte Carlo software RShieldMC[M].Edition A.2017.
12马彦,付元光,邓力,等.三维蒙特卡罗粒子输运前处理软件JLAMT用户使用手册[M].V2.0版.2016.MA Yan,FU Yuanguang,DENG Li,et al.User manual of3D Monte Carlo particle transport processing software JLAMT[M].V2.0.2016.
13杜书华,张树发,冯庭桂,等.输运问题的计算机模拟[M].湖南:湖南科学技术出版社,1988.DU Shuhua,ZHANG Shufa,FENG Tinggui,et al.Computer simulation of transport problems[M].Hunan:Hunan Science and Technology Press,1988.
14郑征,黎辉,丁谦学,等.JMCT-S一次屏蔽计算源项生成功能开发[J].核科学与工程,2017,37(5):805-809.ZHENG Zheng,LI Hui,DING Qianxue,et al.Development on shielding calculation source generation function for JMCT-S[J].Nuclear Science and Engineering,2017,37(5):805-809.
15郑征,丁谦学,王梦琪.一次屏蔽计算TORT程序源项生产方法研究[J].原子能科学与技术,2017,51(10):1905-1909.DOI:10.7538/yzk.2017.youxian.0052.ZHENG Zheng,DING Qianxue,WANG Mengqi.Research on primary shielding calculation source generation method for TORT code[J].Atomic Energy Science and Technology,2017,51(10):1905-1909.DOI:10.7538/yzk.2017.youxian.0052.
2国家核安全局.福岛核事故后核电厂改进行动通用技术要求(试行)[R].北京:国家核安全局,2012.National Nuclear Safety Administration.General technical requirements for nuclear power plant improvement actions after the fukushima accident(trial)[R].Beijing:National Nuclear Safety Administration,2012.
3 European Union.Technical summary on the implementation of comprehensive risk and safety assessments of nuclear power plants in the European Union[R].Brussels:European Commission,2012.DOI:10.1371/journal.ppat.1004184.
4 IAEA.IAEA action plan on nuclear safety[R].Vienna:IAEA,2011.DOI:10.1016/j.esr.2012.11.008.
5 Briesmeister J F MCNP-a general Monte Carlo N-particle transport code[R].Version4C,LA-13709-M.USA:LANL,2000.
6 Rhoades W A,Simpson D B.The TORT threedimensional discrete ordinates neutron/photon transport code[R].ORNL/TM13221.USA:Oak Ridge National Laboratory,1997.
7 Tekin H O,Manici T.Simulations of mass attenuation coefficients for shielding materials using the MCNP-Xcode[J].Nuclear Science and Techniques,2017,28:95.DOI:10.1007/s41365-017-0253-4.
8 Bagheri R,Moghaddam A K,Yousefi A.Gamma-ray shielding study of light to heavyweight concretes using MCNP-4C code[J].Nuclear Science and Techniques,2017,28:15.DOI:10.1007/s41365-016-0167-6.
9 Salimi M,Ghal-Eh N,Amirabadi E A.Characterization of a new shielding rubber for use in neutron-gamma mixed fields[J].Nuclear Science and Techniques,2018,29:36.DOI:10.1007/s41365-018-0371-7.
10 Dong M G,Xue X X,Singh V P,et al.Shielding effectiveness of boron-containing ores in Liaoning province of China against gamma rays and thermal neutrons[J].Nuclear Science and Techniques,2018,29:58.DOI:10.1007/s41365-018-0397-x.
11清华大学.蒙卡软件RShieldMC使用手册[M].A版.2017.Tsinghua University.User manual of Monte Carlo software RShieldMC[M].Edition A.2017.
12马彦,付元光,邓力,等.三维蒙特卡罗粒子输运前处理软件JLAMT用户使用手册[M].V2.0版.2016.MA Yan,FU Yuanguang,DENG Li,et al.User manual of3D Monte Carlo particle transport processing software JLAMT[M].V2.0.2016.
13杜书华,张树发,冯庭桂,等.输运问题的计算机模拟[M].湖南:湖南科学技术出版社,1988.DU Shuhua,ZHANG Shufa,FENG Tinggui,et al.Computer simulation of transport problems[M].Hunan:Hunan Science and Technology Press,1988.
14郑征,黎辉,丁谦学,等.JMCT-S一次屏蔽计算源项生成功能开发[J].核科学与工程,2017,37(5):805-809.ZHENG Zheng,LI Hui,DING Qianxue,et al.Development on shielding calculation source generation function for JMCT-S[J].Nuclear Science and Engineering,2017,37(5):805-809.
15郑征,丁谦学,王梦琪.一次屏蔽计算TORT程序源项生产方法研究[J].原子能科学与技术,2017,51(10):1905-1909.DOI:10.7538/yzk.2017.youxian.0052.ZHENG Zheng,DING Qianxue,WANG Mengqi.Research on primary shielding calculation source generation method for TORT code[J].Atomic Energy Science and Technology,2017,51(10):1905-1909.DOI:10.7538/yzk.2017.youxian.0052.
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