Monte Carlo critical boron concentration search method based on adjoint flux

Xuanxuan BI; Guangyao SUN; Lijuan HAO; Jing SONG; Liqin HU

doi:10.11889/j.0253-3219.2018.hjs.41.070604

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Monte Carlo critical boron concentration search method based on adjoint flux

NUCLEAR ENERGY SCIENCE AND ENGINEERING | 更新时间：2021-05-19

- Monte Carlo critical boron concentration search method based on adjoint flux
- NUCLEAR TECHNIQUES Vol. 41, Issue 7, Article number: 070604(2018)
- 作者机构：
  
  1.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
  2.中国科学技术大学合肥 230026
- 作者简介：
- 基金信息：
  
  National Natural Science Foundation of China;National Special Program for ITER;the President of Chinese Academy of Sciences Foundation for Young Spark Project
- DOI：10.11889/j.0253-3219.2018.hjs.41.070604
  CLC： TL99
- Received：30 September 2017，
  
  Revised：23 March 2018，
  
  Published：10 July 2018
- 稿件说明：
移动端阅览
Xuanxuan BI, Guangyao SUN, Lijuan HAO, et al. Monte Carlo critical boron concentration search method based on adjoint flux[J]. Nuclear techniques, 2018, 41(7): 070604
DOI：

Xuanxuan BI, Guangyao SUN, Lijuan HAO, et al. Monte Carlo critical boron concentration search method based on adjoint flux[J]. Nuclear techniques, 2018, 41(7): 070604 DOI： 10.11889/j.0253-3219.2018.hjs.41.070604.

摘要

临界硼浓度搜索是反应堆设计和物理分析的重要组成部分。本文针对传统搜索方法需要多次临界计算、效率低的问题，发展了一种基于共轭通量的蒙特卡罗临界硼浓度搜索方法。该方法将临界硼浓度搜索视为微扰问题，采用共轭通量法进行微扰计算，并在蒙特卡罗模拟中使用反复裂变几率法计算共轭通量，只需对系统进行一次临界计算，就可以得到系统初始的共轭通量以及有效增殖因子对硼浓度变化的响应系数，使用该响应系数可直接计算得到系统临界硼浓度。西屋公司标准17×17组件模型的数值验证结果表明：本文方法可以有效应用于临界硼浓度搜索。

Abstract

Background

Critical boron concentration search is considered as an important part of reactor design and analysis

but traditional search method requires multiple criticality calculations

hence low efficiency.

Purpose

In order to overcome the disadvantages of the traditional search method

a highly efficient Monte Carlo critical boron concentration search method is developed and verified.

Methods

First of all

the critical boron concentration search is treated as a perturbation problem. Then the adjoint flux method is adopted for perturbation calculation whilst the adjoint flux is calculated by the iterated fission probability method in the Monte Carlo simulation. The adjoint flux and the effective multiplication factor on the boron concentration response coefficients of the initial state can be obtained by only one criticality calculation

and the critical boron concentration is directly derived from the response coefficients. Finally verification is made on the standard Westinghouse 17×17 assembly model.

Results

The numerical results of verification show a good agreement with reference results.

Conclusion

This method can be effectively applied to critical boron concentration search.

关键词

Keywords

references

A Dall'Osso . A neutron balance approach in critical parameter determination . Annals of Nuclear Energy , 2008 . 35 ( 9 ): 1686 - 1694 . DOI: 10.1016/j.anucene.2008.02.008 http://doi.org/10.1016/j.anucene.2008.02.008 https://www.researchgate.net/publication/245135066_A_neutron_balance_approach_in_critical_parameter_determination .

Li R, Zhang L Y, Shi D F, et al. Criticality search of soluble boron iteration in MC code JMCT[C]. International Youth Nuclear Congress (IYNC 2016), Hangzhou, China, 2016. DOI: 10.1016/j.egypro.2017.08.118 http://dx.doi.org/10.1016/j.egypro.2017.08.118 . https://www.researchgate.net/publication/319950518_Criticality_search_of_soluble_boron_iteration_in_MC_code_JMCT

Aaron M B, William R M. Correlated sampling Monte Carlo for critical boron search[C]. MC2015, Nashville, Tennessee, 2015.

李泽光 , 王侃 , 邓景康 . 考虑源扰动效应的高阶蒙特卡罗微扰研究 . 核动力工程 , 2014 . 35 ( 6 ): 6 - 10 . DOI: 10.13832/j.jnpe.2014.06.0006 http://doi.org/10.13832/j.jnpe.2014.06.0006 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hdlg201406002&dbname=CJFD&dbcode=CJFQ .

Zeguang LI , Kan WANG , Jingkang DENG . Research on high-order perturbation calculation method with perturbed source effects . Nuclear Power Engineering , 2014 . 35 ( 6 ): 6 - 10 . DOI: 10.13832/j.jnpe.2014.06.0006 http://doi.org/10.13832/j.jnpe.2014.06.0006 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hdlg201406002&dbname=CJFD&dbcode=CJFQ .

N Yasunobu , M Takamasa . Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations . Journal of Nuclear Science & Technology , 2005 . 42 ( 5 ): 428 - 441 . DOI: 10.3327/jnst.42.428 http://doi.org/10.3327/jnst.42.428 http://cn.bing.com/academic/profile?id=eef0d421381794e46350c87c1eb4e9fc&encoded=0&v=paper_preview&mkt=zh-cn .

H J Shim , C H Kim . Adjoint sensitivity and uncertainty analyses in Monte Carlo forward calculation . Journal of Nuclear Science & Technology , 2011 . 48 ( 12 ): 1453 - 1461 . DOI: 10.1080/18811248.2011.9711838 http://doi.org/10.1080/18811248.2011.9711838 https://www.researchgate.net/publication/233302290_Adjoint_Sensitivity_and_Uncertainty_Analyses_in_Monte_Carlo_Forward_Calculations .

Y Wu . Multi-functional neutronics calculation methodology and program for nuclear design and radiation safety evaluation . Fusion Science and Technology , 2018 . 74 1475162 DOI: 10.1080/15361055.2018.1475162 http://doi.org/10.1080/15361055.2018.1475162 .

Y Wu , Z Chen , L Hu , . Identification of safety gaps for fusion demonstration reactors . Nature Energy , 2016 . 1 16154 DOI: 10.1038/nenergy.2016.154 http://doi.org/10.1038/nenergy.2016.154 http://cn.bing.com/academic/profile?id=186a6f483ba3fc58d871499d094c8222&encoded=0&v=paper_preview&mkt=zh-cn .

Y Wu , J Song , H Zheng , . CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC . Annals of Nuclear Energy , 2015 . 82 161 - 168 . DOI: 10.1051/snamc/201406022 http://doi.org/10.1051/snamc/201406022 http://cn.bing.com/academic/profile?id=4d9eaa436d37ed21f89972fad8241b7e&encoded=0&v=paper_preview&mkt=zh-cn .

Y Wu , Team FDS . CAD-based interface programs for fusion neutron transport simulation . Fusion Engineering and Design , 2009 . 84 ( 7-11 ): 1987 - 1992 . DOI: 10.1016/j.fusengdes.2008.12.041 http://doi.org/10.1016/j.fusengdes.2008.12.041 http://cn.bing.com/academic/profile?id=a77ec550c8121db6217f391aef45c87b&encoded=0&v=paper_preview&mkt=zh-cn .

吴宜灿 , 宋婧 , 胡丽琴 , . 超级蒙特卡罗核计算仿真软件系统SuperMC . 核科学与工程 , 2016 . 36 ( 1 ): 62 - 71 . http://www.wanfangdata.com.cn/details/detail.do?_type=perio&id=kjcgglyyj201506027 .

Yican WU , Jing SONG , Liqin HU , . Super Monte Carlo simulation program for nuclear and radiation process:SuperMC . Nuclear Science and Engineering , 2016 . 36 ( 1 ): 62 - 71 . http://www.wanfangdata.com.cn/details/detail.do?_type=perio&id=kjcgglyyj201506027 .

Y Wu . Conceptual design of the China fusion power plant FDS-Ⅱ . Fusion Engineering and Design , 2008 . 83 ( 10-12 ): 1 https://www.researchgate.net/publication/245221349_Conceptual_design_of_the_China_fusion_power_plant_FDS-II .

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 http://cn.bing.com/academic/profile?id=062f013472e837cb50be1538346997c0&encoded=0&v=paper_preview&mkt=zh-cn .

Y Wu , Y Bai , Y Song , . Development strategy and conceptual design of China Lead-based Research Reactor . Annals of Nuclear Energy , 2016 . 87 511 - 516 . DOI: 10.1016/j.anucene.2015.08.015 http://doi.org/10.1016/j.anucene.2015.08.015 http://cn.bing.com/academic/profile?id=351ce9fcd0fc463c0e4cabed28a707e1&encoded=0&v=paper_preview&mkt=zh-cn .

Y Wu . Design and R & D progress of China Lead-Based Reactor for ADS research facility . Engineering , 2016 . 2 ( 1 ): 124 - 131 . DOI: 10.1016/J.ENG.2016.01.023 http://doi.org/10.1016/J.ENG.2016.01.023 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=goch201601030&dbname=CJFD&dbcode=CJFQ .

Q Huang , N Baluc , Y Dai , . Recent progress of R & D activities on reduced activation ferritic/martensitic steels . Journal of Nuclear Materials , 2013 . 442 ( 1-3 ): S2 - S8 . DOI: 10.1016/j.jnucmat.2012.12.039 http://doi.org/10.1016/j.jnucmat.2012.12.039 https://www.researchgate.net/publication/260848194_Recent_progress_of_RD_activities_on_reduced_activation_ferriticmartensitic_steels .

Q Huang , C Li , Y Li , . Progress in development of China low activation martensitic steel for fusion application . Journal of Nuclear Materials , 2007 . s367-370 ( 10 ): 142 - 146 . DOI: 10.1016/j.jnucmat.2007.03.153 http://doi.org/10.1016/j.jnucmat.2007.03.153 http://cn.bing.com/academic/profile?id=edd92270db71bf89afdea5fa8ee7891b&encoded=0&v=paper_preview&mkt=zh-cn .

Q Huang . Status and improvement of CLAM for nuclear application . Nuclear Fusion , 2017 . 57 086042 DOI: 10.1088/1741-4326/aa763f http://doi.org/10.1088/1741-4326/aa763f https://www.researchgate.net/publication/317287814_Status_and_improvement_of_CLAM_for_nuclear_application .

Y Wu . Design status and development strategy of China liquid lithium-lead blankets and related material technology . Journal of Nuclear Materials , 2007 . 367 ( 4 ): 1410 - 1415 . DOI: 10.1016/j.jnucmat.2007.04.031 http://doi.org/10.1016/j.jnucmat.2007.04.031 http://cn.bing.com/academic/profile?id=09747f2edfe120078a018c243f97dbda&encoded=0&v=paper_preview&mkt=zh-cn .

Wu Y, Liu C, Song G, et al. Development of high intensity D-T fusion neutron generator (HINEG)[C]. European Physical Journal Web of Conferences, European Physical Journal Web of Conferences, 2017: 03006. DOI: 10.1051/epjconf/201715303006 http://dx.doi.org/10.1051/epjconf/201715303006 .

吴宜灿 , 刘超 , 宋钢 , . 强流氘氚聚变中子源HINEG设计研究 . 核科学与工程 , 2016 . 36 ( 1 ): 77 - 83 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hkxy201601011&dbname=CJFD&dbcode=CJFQ .

Yican WU , Chao LIU , Gang SONG , . Design study of high intensity D-T fusion neutron generator HINGE . Nuclear Science and Engineering , 2016 . 36 ( 1 ): 77 - 83 . http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hkxy201601011&dbname=CJFD&dbcode=CJFQ .

谢仲生 , 邓力 . 中子输运理论数值计算方法 , : 西安西北工业大学出版社 , 2005 . 303 - 345 .

Zhongsheng XIE , Li DENG . Neutron transport theory numerical method , : Xi'an Northwestern Polytechnical University Press , 2005 . 303 - 345 .

Hurwitz H. Physical interpretation of the adjoint flux: iterated fission probability[M]. Naval Reactor Physics Handbook I, U. S. Atomic Energy Commission, 1964: 864-869.

丘意书 , 梁金刚 , 王侃 . 基于反复裂变几率法的敏感性分析初步研究 . 核动力工程 , 2014 . 35 ( S2 ): 83 - 86 . DOI: 10.13832/j.jnpe.2014.S2.0083 http://doi.org/10.13832/j.jnpe.2014.S2.0083 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hdlg2014s2023&dbname=CJFD&dbcode=CJFQ .

Yishu QIU , Jingang LIANG , Kan WANG . Preliminary study of sensitivity analysis based on iterated fission probability method . Nuclear Power Engineering , 2014 . 35 ( S2 ): 83 - 86 . DOI: 10.13832/j.jnpe.2014.S2.0083 http://doi.org/10.13832/j.jnpe.2014.S2.0083 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hdlg2014s2023&dbname=CJFD&dbcode=CJFQ .

刘勇 , 曹良志 , 吴宏春 , . 基于经典微扰理论的特征值灵敏度和不确定性分析 . 原子能科学技术 , 2015 . 49 ( 7 ): 1247 - 1253 . DOI: 10.7538/yzk.2015.49.07.1247 http://doi.org/10.7538/yzk.2015.49.07.1247 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201507016&dbname=CJFD&dbcode=CJFQ .

Yong LIU , Liangzhi CAO , Hongchun WU , . Eigenvalue sensitivity and uncertainty analysis based on classical perturbation theory . Atomic Energy Science and Technology , 2015 . 49 ( 7 ): 1247 - 1253 . DOI: 10.7538/yzk.2015.49.07.1247 http://doi.org/10.7538/yzk.2015.49.07.1247 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=yzjs201507016&dbname=CJFD&dbcode=CJFQ .

佘顶, 梁金刚, 吴高晨, 等. 堆用蒙卡程序RMC-Beta2. 0用户使用手册[CP/DK]. 北京: 清华

REAL, 2013: 18-19. SHE Ding, LIANG Jingang, WU Gaochen, et al. Monte Carlo code for reactor analysis RMC-Beta2. 0 user manual[CP/DK]. Beijing: Tsinghua University REAL, 2013: 18-19.

甘佺 , 吴斌 , 宋婧 , . 基于参数的可视化裂变堆芯蒙特卡罗自动建模方法 . 核技术 , 2016 . 39 ( 6 ): 060501 DOI: 10.11889/j.0253-3219.2016.hjs.39.060501 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.060501 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract603.shtml .

Quan GAN , Bin WU , Jing SONG , . Rapid parameter-based and visual Monte Carlo modeling method of fission reactor core . Nuclear Techniques , 2016 . 39 ( 6 ): 060501 DOI: 10.11889/j.0253-3219.2016.hjs.39.060501 http://doi.org/10.11889/j.0253-3219.2016.hjs.39.060501 http://www.j.sinap.ac.cn/hejishu/CN/abstract/abstract603.shtml .

Q Gan , B Wu , S Yu , . CAD-based hierarchical geometry conversion method for modeling of fission reactor cores . Annals of Nuclear Energy , 2016 . 94 369 - 375 . DOI: 10.1016/j.anucene.2016.03.013 http://doi.org/10.1016/j.anucene.2016.03.013 http://cn.bing.com/academic/profile?id=cf712ecc7b11b7fa4c72a8bc6790ee2e&encoded=0&v=paper_preview&mkt=zh-cn .

X L Pan , J Q Wang , R Yuan , . Biasing transition rate method based on direct MC simulation for probabilistic safety assessment . Nuclear Science and Techniques , 2017 . 28 ( 7 ): 91 DOI: 10.1007/s41365-017-0255-2 http://doi.org/10.1007/s41365-017-0255-2 http://kns.cnki.net/KCMS/detail/detail.aspx?filename=hkxj201707012&dbname=CJFD&dbcode=CJFQ .

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