基于自动网格划分与权窗平滑的自适应减方差方法

郑华庆; 李斌; 宋婧; 郝丽娟; 龙鹏程; 胡丽琴; 吴宜灿

doi:10.11889/j.0253-3219.2016.hjs.39.090502

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基于自动网格划分与权窗平滑的自适应减方差方法

核物理、交叉学科研究 | 更新时间：2021-05-24

- 基于自动网格划分与权窗平滑的自适应减方差方法
- Adaptive variance reduction method based on automatic mesh generating and weight window smoothing
- 核技术 2016年39卷第9期文章编号：090502
- 作者机构：
  
  中国科学院核能安全技术研究所中子输运理论与辐射安全重点实验室合肥 230031
- 作者简介：
  
  [ "郑华庆,男,1984年出生,2015年于中国科学院大学获博士学位,现从事蒙特卡罗粒子输运计算研究工作", "ZHENG Huaqing, male, born in 1984, graduated from University of Chinese Academy of Sciences with a doctor’s degree in 2015, engaged in the research of Monte Carlo particle transport simulation" ]
  吴宜灿,E-mail:yican.wu@fds.org.cn WU Yican, E-mail:yican.wu@fds.org.cn
- 基金信息：
  
  中国科学院战略性先导科技专项(No.XDA03040000);国家磁约束核聚变能发展研究专项(No.2014GB112001);国家自然科学基金(No.11305205、No.11305203、No.11405204)
- DOI：10.11889/j.0253-3219.2016.hjs.39.090502
  中图分类号： TL7
- 收稿日期：2016-02-11，
  
  修回日期：2016-03-22，
  
  纸质出版日期：2016-09
- 稿件说明：
移动端阅览
郑华庆, 李斌, 宋婧, 等. 基于自动网格划分与权窗平滑的自适应减方差方法[J]. 核技术, 2016,39(9):090502

Huaqing ZHENG, Bin LI, Jing SONG, et al. Adaptive variance reduction method based on automatic mesh generating and weight window smoothing[J]. Nuclear techniques, 2016, 39(9): 090502
郑华庆, 李斌, 宋婧, 等. 基于自动网格划分与权窗平滑的自适应减方差方法[J]. 核技术, 2016,39(9):090502 DOI： 10.11889/j.0253-3219.2016.hjs.39.090502.

Huaqing ZHENG, Bin LI, Jing SONG, et al. Adaptive variance reduction method based on automatic mesh generating and weight window smoothing[J]. Nuclear techniques, 2016, 39(9): 090502 DOI： 10.11889/j.0253-3219.2016.hjs.39.090502.

摘要

如何更高效发挥减方差的作用是蒙特卡罗方法在先进核能系统屏蔽分析应用中的研究热点之一。本文发展了一种基于自动网格划分与权窗平滑的自适应减方差方法，在蒙特卡罗和确定论耦合的一致性伴随驱动的重要性抽样方法（Consistent Adjoint Driven Importance Sampling

CADIS）基础上，利用计算机辅助设计（Computer Aided Design

CAD）自动转换和自由程自动划分

网格，通过确定论方法伴随预计算，实现基于伴随通量的区域权窗参数自动配置，并对伴随通量变化剧烈区域进行权窗平滑处理，保证了粒子在不同区域的有效偏倚，进一步提高计算的效率，从而解决大空间蒙特卡罗计算难以收敛的问题。该方法已初步应用于中国铅基反应堆（China Lead-based Reactor

CLEAR）堆顶盖的屏蔽计算分析，该案例具有结构复杂、屏蔽材料厚重的特点，测试结果表明本方法将计算效率提高近10倍。

Abstract

Background

In the radiation shielding analysis of advanced nuclear reactor with Monte Carlo method

it is one of the researches focuses on using variance reduction methods more effectively.

Purpose

An adaptive variance reduction method based on automatic mesh generating and weight window smoothing is developed in this paper.

Methods

With hybrid calculation of Monte Carlo method and deterministic theory

consistent adjoint driven importance sampling(CADIS)method was developed by automatic mesh generating with computer aided design(CAD)and pre-calculation of free path.The adjoint flux calculation results with deterministic method are treated as core values to generate source biasing parameters and weight window parameters in the form of mesh.And smooth treatment is introduced for alleviating the lower bound of weight window violent change to make sure the efficiency of particle bias in different areas and improve calculation efficiency.This method can solve the convergence problem in Monte Carlo simulation with large space geometry.

Results

The adaptive method has been applied in the shielding calculation of China lead-based reactor(CLEAR)cover with complex geometry and massive shielding body.The result showed that the computing efficiency is improved by nearly 10 times.

Conclusion

The adaptive variance reduction method can be applied to the shielding calculation of advanced nuclear fission reactor.

关键词

Keywords

references

J C Wagner , D E Peplow , S W Mosher , . Review of hybrid(deterministic/Monte Carlo) radiation transport methods, codes, and applications at Oak Ridge National Laboratory . Progress in Nuclear Science and Technology , 2011 . 2 808 - 814 . DOI: 10.15669/pnst.2.808 http://doi.org/10.15669/pnst.2.808 .

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

L Qiu , Y Wu , B Xiao , . A low aspect ratio tokamak transmutation system . Nuclear Fusion , 2000 . 40 629 - 633 . DOI: 10.1016/S0920-3796(98)00312-3 http://doi.org/10.1016/S0920-3796(98)00312-3 .

Y Wu , J Qian , J Yu . The fusion-driven hybrid system and its material selection . Journal of Nuclear Materials , 2002 . 307-311 1629 - 1636 . DOI: 10.1016/S0022-3115(02)01272-2 http://doi.org/10.1016/S0022-3115(02)01272-2 .

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

Y Wu , Team FDS . Conceptual design of the China fusion power plant FDS-Ⅱ . Fusion Engineering and Design , 2008 . 83 ( 10-12 ): 1683 - 1689 . DOI: 10.1016/j.fusengdes.2008.06.048 http://doi.org/10.1016/j.fusengdes.2008.06.048 .

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

Y Wu , Team FDS . Conceptual design and testing strategy of a dual functional lithium-lead test blanket module in ITER and EAST . Nuclear Fusion , 2007 . 47 ( 11 ): 1533 - 1539 . DOI: 10.1088/0029-5515/47/11/015 http://doi.org/10.1088/0029-5515/47/11/015 .

Y Wu , Team FDS . CAD-based interface programs for fusion neutron transport simulation . Fusion Engineering and Design , 2009 . 84 1987 - 1992 . DOI: 10.1016/j.fusengdes.2008.12.041 http://doi.org/10.1016/j.fusengdes.2008.12.041 .

Y Wu . Design status and development strategy of China liquid lithium-lead blankets and related material technology . Journal of Nuclear Materials , 2007 . 367-370 1410 - 1415 . DOI: 10.1016/j.jnucmat.2007.04-031 http://doi.org/10.1016/j.jnucmat.2007.04-031 .

Y Wu , Team FDS . Design analysis of the China Dual-Functional Lithium Lead(DFLL) test blanket module in ITER . Fusion Engineering and Design , 2007 . 82 1893 - 1903 . DOI: 10.1016/j.fusengdes.2007.08.012 http://doi.org/10.1016/j.fusengdes.2007.08.012 .

Y Wu , J Song , H Zheng , . CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC . Annual of Nuclear Energy , 2015 . 82 161 - 168 . DOI: 10.1016/j.anucene.2014.08.058 http://doi.org/10.1016/j.anucene.2014.08.058 .

J Song , G Sun , Z Chen , . Benchmarking of CAD-based SuperMC with ITER Benchmark model . Fusion Engineering and Design , 2014 . 89 2499 - 2503 . DOI: 10.1016/j.fusengdes.2014.05.003 http://doi.org/10.1016/j.fusengdes.2014.05.003 .

孙光耀 , 宋婧 , 郑华庆 , . 超级蒙特卡罗软件SuperMC2.0中子输运计算校验 . 原子能科学技术 , 2013 . 47 ( 增2 ): 140 - 145 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2013S2030.htm .

Guangyao SUN , Jing SONG , Huaqing ZHENG , . Benchmark of neutron transport simulation capability of super Monte Carlo calculation program SuperMC2 . Atomic Energy Science and Technology , 2013 . 47 ( Suppl 2 ): 140 - 145 . http://www.cnki.com.cn/Article/CJFDTOTAL-YZJS2013S2030.htm .

H Hu , Y Wu , M Chen , . Benchmarking of SNAM with the ITER 3D model . Fusion Engineering and Design , 2007 . 82 2867 DOI: 10.1016/j.fusengdes.2007.06.015 http://doi.org/10.1016/j.fusengdes.2007.06.015 .

P Long , J Zou , S Huang , . Development and application of SN auto-modeling tool SNAM 2 . Fusion Engineering and Design , 2010 . 85 1113 - 1116 . DOI: 10.1016/j.fusengdes.2010.02.016 http://doi.org/10.1016/j.fusengdes.2010.02.016 .

X-5 Monte Carlo Team. MCNP - a general Monte Carlo N-particle transport Code[R]. Version 5. Report LA-UR-03-1987, Los Alamos National Laboratory, April 24, 2003

詹文龙 , 徐瑚珊 . 未来先进裂变能—ADS嬗变系统 . 中国科学院院刊 , 2012 . 27 ( 3 ): 375 - 381 . http://www.cnki.com.cn/Article/CJFDTOTAL-KYYX201203018.htm .

Wenlong ZHAN , Hushan XU . Advanced fission energy program - ADS transmutation system . Bulletin of Chinese Academy of Sciences , 2012 . 27 ( 3 ): 375 - 381 . http://www.cnki.com.cn/Article/CJFDTOTAL-KYYX201203018.htm .

Y Wu , Y Bai , Y Song , . Development strategy and conceptual design of China lead-based research reactor . Annals Nuclear Energy , 2016 . 87 511 - 516 . DOI: 10.1016/j.anucene.2015.08.015 http://doi.org/10.1016/j.anucene.2015.08.015 .

吴宜灿 , 柏云清 , 宋勇 , . 中国铅基研究反应堆概念设计研究 . 核科学与工程 , 2014 . 34 ( 2 ): 56 - 63 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201402009.htm .

Yican WU , Yunqing BAI , Yong SONG , . Conceptual design of China lead-based research reactor CLEAR-I . Nuclear Science and Engineering , 2014 . 34 ( 2 ): 56 - 63 . http://www.cnki.com.cn/Article/CJFDTOTAL-HKXY201402009.htm .

Wu Y, Bai Y, Wang W, et al. Overview of China lead-alloy cooled rector development and ADS program in China[C]. POWER - the 9th International Topical Meeting on Nuclear Thermal-hydraulics, Operation and Safety (NUTHOS-9), Kaohsiung, Taiwan, September 9‒13, 2012

Yang Q, Li B, Chen C, et al. Primary shielding design and analysis for CLEAR-I[C]. 21st International Conference on Nuclear Engineering (ICONE-21), Chengdu, Sichuan, China, July 29‒August 2, 2013

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