关键词: 蒙特卡罗方法/
临界计算/
全局计数
English Abstract
Algorithm researches for efficient global tallying in criticality calculation of Monte Carlo method
ShangGuan Dan-Hua1,Deng Li1,
Li Gang1,
Zhang Bao-Yin1,
Ma Yan1,
Fu Yuan-Guang2,
Li Rui2,
Hu Xiao-Li2
1.Institute of Applied Physics and Computational Mathematics, Beijing 100094, China;
2.CAEP Software Center for High Performance Numerical Simulation, Beijing 100083, China
Fund Project:Project supported by the special projects of the National Energy Administration, China(Grant No. 2015ZX06002008), the Key Program of the National Natural Science Foundation of China (Grant No. 91118001), the State Administration of Science, Technology and Industry for National Defense, PRC(Grant No.[2012]1523), the Science Foundation of China Academy of Engineering Physics (Grant No. 2014B0202029), and the National High Technology Research and Development Program of China (Grant No. 2012AA01A303).Received Date:06 September 2015
Accepted Date:20 December 2015
Published Online:05 March 2016
Abstract:Based on the research of the uniform fission site algorithm, the uniform tally density algorithm and the uniform track number density algorithm are proposed and compared with the original uniform fission site algorithm in this paper for seeking high performance of global tallying in Monte Carlo criticality calculation. Because reducing the largest uncertainties to an acceptable level simply by running a large number of neutron histories is often prohibitively expensive, the researches are indispensable for the calculation to reach the goal of practical application (the so called 95/95 standard). Using the global volume-averaged cell flux tally and energy deposition tally of the pin-by-pin model of Dayawan nuclear reactor as two examples, these new algorithms show better results. Although the uniform tally density algorithm has the best performance, the uniform track number density algorithm still has the advantage of being applicable to any type of tally, which is based on the track length estimator without any modification. All the algorithms are realized in a recently developed parallel Monte Carlo particle transport code JMCT.
Keywords: Monte Carlo method/
criticality calculation/
global tally
