基于计数辅助树的蒙特卡罗粒子输运计算大规模计数方法

doi:10.11889/j.0253-3219.2016.hjs.39.100502

Nuclear Techniques ›› 2016, Vol. 39 ›› Issue (10): 100502-100502.doi: 10.11889/j.0253-3219.2016.hjs.39.100502

• NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH • Previous Articles Next Articles

Tally assist tree-based method for scoring massive tallies in Monte Carlo particle transport calculation

ZHANG Shu^1,2, HAO Lijuan², SONG Jing², WU Bin², SUN Guangyao²

1 School of Nuclear Science and Technology, University of Science and Technology of China, Hefei 230027, China;
2 Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China

Received:2016-05-26 Revised:2016-07-07 Online:2016-10-10 Published:2016-10-13
Supported by:
Supported by Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA03040000), National Natural Science Foundation of China (No.11305203), National Special Program for ITER (No.2014GB1120000)

Abstract

Abstract:

Background: Traditional Monte Carlo particle transport calculation codes traverse all the tally cards to find which tallies should be scored at the end of each simulation step. The run time of this procedure almost grows linearly with the number of total tally number. When the tally number is large, the tally procedure costs far more time than the transport calculation. Purpose: This paper proposed a tree-based method for scoring massive tallies. Methods: The method builds a tally assist tree that all the nodes map one-for-one to the geometry cells. All the tally information read from the input file is stored in the tree. At the end of each simulation step, by mapping the geometry information of the cell where the particle is currently in to a node in the tree, the tallies need to be scored is directly retrieved from the node. Results: To test the proposed method, the run time of the Hoogenboom benchmark reactor model with different tally numbers is measured. Conclusion: The results show that this method can improve the computation efficiency of massive tally problems.

Key words: Monte Carlo, Particle transport, Tally assist tree, Massive tallies

CLC Number:

TL329.2

ZHANG Shu, HAO Lijuan, SONG Jing, WU Bin, SUN Guangyao. Tally assist tree-based method for scoring massive tallies in Monte Carlo particle transport calculation[J].Nuclear Techniques, 2016, 39(10): 100502-100502.

References

1 X-5 Monte Carlo Team. MCNP-a general Monte Carlo N-particle transport code[M]. Los Alamos Scientific Laboratory, 2003

2 Romano P K, Forget B. The OpenMC Monte Carlo particle transport code[J]. Annals of Nuclear Energy, 2013, 51(1):274-281. DOI:10.1016/j.anucene.2012.06.040

3 Wang K, Li Z G, She D, et al. RMC-a Monte Carlo code for reactor core analysis[J]. Annals of Nuclear Energy, 2015, 82:121-129. DOI:10.1016/j.anucene.2014.08.048

4 邓力, 李刚, 张宝印, 等. JMCT蒙特卡罗中子-光子输运程序全堆芯pin-by-pin模型的模拟[J]. 原子能科学技术, 2014, 48(6):1061-1066 DENG Li, LI Gang, ZHANG Baoyin, et al. Simulation of full-core pin-by-pin model by JMCT Monte Carlo neutron-photon transport code[J]. Atomic Energy Science and Technology, 2014, 48(6):1061-1066

5 Veen D V, Hoogenboom J E. Efficiency improvement of local power estimation in the general purpose Monte Carlo code MCNP[J]. Progress in Nuclear Science and Technology, 2011, 2(1):866-871

6 She D, Qiu Y. Improved methods of handling massive tallies in reactor Monte Carlo code RMC[R]. Proceeding 2013 International Conference on Mathematics & Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, Idaho, May 5-9, 2013

7 Wu Y, Song J, Zheng H Q, et al. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC[J]. Annals of Nuclear Energy, 2015, 82(1):161-168. DOI:10.1016/j.anucene.2014.08.058

8 Wu Y, FDS Team. CAD-based interface program for fusion neutron transport simulation[J]. Fusion Engineering and Design, 2009, 84(7-11):1987-1992. DOI:10.1016/j.fusengdes.2008.12.041

9 Wu Y, FDS Team. Conceptual design activities of FDS series fusion power plants in China[J]. Fusion Engineering and Design, 2006, 81(23-24):2713-2718. DOI:10.1016/j.fusengdes.2006.07.068

10 Wu Y, Jiang J, Wang M, et al. A fusion-driven subcritical system concept based on viable technologies[J]. Nuclear Fusion, 2011, 51(10):103036. DOI:10.1088/0029-5515/51/10/103036

11 Qiu L, Wu Y, Xiao B. A low aspect ratio tokamak transmutation system[J]. Nuclear Fusion, 2000, 40(3Y):629-633. DOI:10.1088/0029-5515/40/3Y/325

12 Wu Y, FDS Team. Design analysis of the China Dual-Functional Lithium Lead (DFLL) test blanket module in ITER[J]. Fusion Engineering and Design, 2007, 82(1):1893-1903. DOI:10.1016/j.fusengdes.2007.08. 012

13 Wu Y, FDS Team. Conceptual design of the China fusion power plant FDS-Ⅱ[J]. Fusion Engineering and Design, 2008, 83(1):1683-1689. DOI:10.1016/j.fusengdes.2008. 06.048

14 Wu Y, FDS Team. Fusion-based hydrogen production reactor and its material selection[J]. Journal of Nuclear Materials, 2009, 386-388:122-126. DOI:10.1016/j.jnucmat.2008.12.075

15 Wu Y, FDS Team. Design status and development strategy of China liquid lithium-lead blankets and related material technology[J]. Journal of Nuclear Materials, 2007, 367-370:1410-1415. DOI:10.1016/j.jnucmat.2007.04. 031

16 Li Y, Lu L, Ding A, et al. Benchmarking of MCAM4.0 with the ITER 3D model[J]. Fusion Engineering and Design, 2007, 82(15-24):2861-2866. DOI:10.1016/j.fusengdes.2007.02.022

17 Song J, Sun G Y, Chen Z P, et al. Benchmarking of CAD-based SuperMC with ITER benchmark model[J]. Fusion Engineering and Design, 2014, 89(1):2499-2503. DOI:10.1016/j.fusengdes.2014.05.003

18 Zhang B H, Song J, Sun G Y, et al. Criticality validation of SuperMC with ICSBEP[J]. Annals of Nuclear Energy, 2016, 87:494-499. DOI:10.1016/j.anucene.2015.10.004

19 Andrei A. Modern C++ design:generic programming and design patterns applied[M]. Boston:Addison-Wesley, 2001

20 Hoogenboom J E, Martin W R. The Monte Carlo performance benchmark test-aims, specifications and first results[R]. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Rio de Janeiro, Brazil, May 8-12, 2011

21 刘鸿飞, 张彬航, 张澍, 等. 基于Hoogenboom基准模型的SuperMC全堆芯计算能力校验[J]. 核技术, 2016, 39(4):040604. DOI:10.11889/j.0253-3219.2016.hjs.39. 040604 LIU Hongfei, ZHANG Binhang, ZHANG Shu, et al. Full reactor core calculation performance validation of SuperMC based on Hoogenboom benchmark[J]. Nuclear Techniques, 2016, 39(4):040604. DOI:10.11889/j. 0253-3219.2016.hjs.39.040604

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Tally assist tree-based method for scoring massive tallies in Monte Carlo particle transport calculation

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