三维瞬态输运程序在中子点火中的应用
Application of 3D Time-dependent Transport Code in Neutron Initiation
-
摘要: 基于广义半马尔科夫过程模拟方法开发了一套三维中子输运瞬态蒙特卡罗程序GSMP3D，该程序使用ACE格式连续截面，适用于随机中子场瞬态和强中子场瞬态问题的求解。以美国劳伦斯利弗莫尔国家实验室(LLNL)和洛斯阿拉莫斯国家实验室(LANL)提供的中子点火对算模型为例，对比了GSMP3D与美国点火程序Mercury的计算结果，二者吻合很好，GSMP3D不仅给出了中子点火概率，还提供了定态点火实验的中子爆发等待时间的统计结果。表明该程序可用于处理中子点火问题。Abstract: Based on the generalized semi-Markov process simulation method, the 3D time-dependent transport code GSMP3D was developed. It used continuous-energy nuclear and atomic data libraries in ACE format. It is suitable for the transient cases of both stochastic and intense neutron fields. A suite of test problems developed by researchers at LANL and LLNL were used to validate probability of initiation methods. The results obtained from GSMP3D agree well with the results obtained from Mercury and MCNP. Both the initiation probability and the burst waiting time of neutron initiation were predicted by this new code. It shows that it is suitable for neutron initiation problem.
-
Keywords:
- space-time neutron kinetics ,
- neutron initiation ,
- Monte Carlo method
-
-
[1] BELL G I. Probability distribution of neutrons and precursors in a multiplying assembly[J]. Annals of Physics, 1963, 21(2): 243-283. [2] BELL G I. On the stochastic theory of neutron transport[J]. Nuclear Science and Engineering, 1965, 21(3): 390-401. [3] HUMBERT P. Stochastic neutronics with PANDA deterministic code[C]∥Nuclear Mathematical and Computational Sciences: A Century in Review. Gatlinburg, TN, USA: [s. n.], 2003: 6-11. [4] GREENMAN G M, PROCASSINI R J, CLOUSE C J. A Monte Carlo method for calculating initiation probability[C]∥Proceedings of the Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications.[S. l.]: [s. n.], 2007: 16-19. [5] XIAO G. The simulation of probability distribution of the burst waiting time of neutron initiation[J]. Nuclear Science and Engineering, 2011, 169(1): 56-67. [6] 杨俊云，肖刚，应阳君. 点堆中子动力学方程的蒙特卡罗方法[J]. 核动力工程，2015，36(6): 4-9. YANG Junyun, XIAO Gang, YING Yangjun. A Monte Carlo method for solving point reactor kinetics equation[J]. Nuclear Power Engineering, 2015, 36(6): 4-9（in Chinese）. [7] NOLEN S D, SPRIGGS G D. Estimation of the neutron chain-length distribution in subcritical systems using a point Monte Carlo code[J]. Annals of Nuclear Energy, 2001, 28(5): 509-512. [8] VERBEKE J M, HAGMANN C, WRIGHT D. Simulation of neutron and gamma ray emission from fission and photo fission, UCRL-AR-228518[R]. US: Lawrence Livermore National Laboratory, 2010. [9] SPRIGGS G D, BUSCH R D, SAKURAI T, et al. The equivalent fundamental-mode source[J]. Annals of Nuclear Energy, 1999, 26(3): 237-264.
计量
- 文章访问数: 187
- HTML全文浏览量: 0
- PDF下载量: 1073
下载:
