基于共轭通量的蒙特卡罗临界硼浓度搜索方法

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

Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (7): 70604-070604.doi: 10.11889/j.0253-3219.2018.hjs.41.070604

• NUCLEAR PHYSICS, INTERDISCIPLINARY RESEARCH • Previous Articles Next Articles

Monte Carlo critical boron concentration search method based on adjoint flux

BI Xuanxuan^1,2, SUN Guangyao¹, HAO Lijuan¹, SONG Jing¹, HU Liqin^1,2

1. Key Laboratory of Neutronics and Radiation Safety, Institute of Nuclear Energy Safety Technology, Chinese Academy of Sciences, Hefei 230031, China;
2. University of Science and Technology of China, Hefei 230026, China

Received:2017-09-30 Revised:2018-03-23 Online:2018-07-10 Published:2018-07-07
Supported by:
Supported by National Natural Science Foundation of China (No.11605233), National Special Program for ITER (No.2014GB112000), President of Chinese Academy of Sciences Foundation for Young Spark Project (No.YZJJ201618)

Abstract

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.

Key words: Criticality search, Adjoint flux, Iterated fission probability, Perturbation, SuperMC

CLC Number:

TL99

BI Xuanxuan, SUN Guangyao, HAO Lijuan, SONG Jing, HU Liqin. Monte Carlo critical boron concentration search method based on adjoint flux[J].Nuclear Techniques, 2018, 41(7): 70604-070604.

References

1 Dall'Osso A. A neutron balance approach in critical parameter determination[J]. Annals of Nuclear Energy, 2008, 35(9):1686-1694. DOI:10.1016/j.anucene.2008.02. 008.
2 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.
3 Aaron M B, William R M. Correlated sampling Monte Carlo for critical boron search[C]. MC2015, Nashville, Tennessee, 2015.
4 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[J]. 核动力工程, 2014, 35(6):6-10. DOI:10.13832/j.jnpe.2014.06.0006. LI Zeguang, WANG Kan, DENG Jingkang. Research on high-order perturbation calculation method with perturbed source effects[J]. Nuclear Power Engineering, 2014, 35(6):6-10. DOI:10.13832/j.jnpe.2014.06.0006.
5 Yasunobu N, Takamasa M. Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations[J]. Journal of Nuclear Science & Technology, 2005, 42(5):428-441. DOI:10.3327/jnst.42.428.
6 Shim H J, Kim C H. Adjoint sensitivity and uncertainty analyses in Monte Carlo forward calculation[J]. Journal of Nuclear Science & Technology, 2011, 48(12):1453-1461. DOI:10.1080/18811248.2011.9711838.
7 Wu Y. Multi-functional neutronics calculation methodology and program for nuclear design and radiation safety evaluation[J]. Fusion Science and Technology, 2018, 74:1475162. DOI:10.1080/15361055.2018.1475162.
8 Wu Y, Chen Z, Hu L, et al. Identification of safety gaps for fusion demonstration reactors[J]. Nature Energy, 2016, 1:16154. DOI:10.1038/nenergy.2016.154.
9 Wu Y, Song J, Zheng H, et al. CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC[J]. Annals of Nuclear Energy, 2015, 82:161-168. DOI:10.1051/snamc/201406022.
10 Wu Y, FDS Team. CAD-based interface programs for fusion neutron transport simulation[J]. Fusion Engineering and Design, 2009, 84(7-11):1987-1992. DOI:10.1016/j.fusengdes.2008.12.041.
11 吴宜灿, 宋婧, 胡丽琴, 等. 超级蒙特卡罗核计算仿真软件系统SuperMC[J]. 核科学与工程, 2016, 36(1):62-71. WU Yican, SONG Jing, HU Liqin, et al. Super Monte Carlo simulation program for nuclear and radiation process:SuperMC[J]. Nuclear Science and Engineering, 2016, 36(1):62-71.
12 Wu Y. Conceptual design of the China fusion power plant FDS-Ⅱ[J]. Fusion Engineering and Design, 2008, 83(10-12):1.
13 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.
14 Wu Y, Bai Y, Song Y, et al. Development strategy and conceptual design of China Lead-based Research Reactor[J]. Annals of Nuclear Energy, 2016, 87:511-516. DOI:10.1016/j.anucene.2015.08.015.
15 Wu Y. Design and R&D progress of China Lead-Based Reactor for ADS research facility[J]. Engineering, 2016, 2(1):124-131. DOI:10.1016/J.ENG.2016.01.023.
16 Huang Q, Baluc N, Dai Y, et al. Recent progress of R&D activities on reduced activation ferritic/martensitic steels[J]. Journal of Nuclear Materials, 2013, 442(1-3):S2-S8. DOI:10.1016/j.jnucmat.2012.12.039.
17 Huang Q, Li C, Li Y, et al. Progress in development of China low activation martensitic steel for fusion application[J]. Journal of Nuclear Materials, 2007, s367-370(10):142-146. DOI:10.1016/j.jnucmat.2007.03. 153.
18 Huang Q. Status and improvement of CLAM for nuclear application[J]. Nuclear Fusion, 2017, 57:086042. DOI:10.1088/1741-4326/aa763f.
19 Wu Y. Design status and development strategy of China liquid lithium-lead blankets and related material technology[J]. Journal of Nuclear Materials, 2007, 367(4):1410-1415. DOI:10.1016/j.jnucmat.2007.04.031.
20 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.
21 吴宜灿, 刘超, 宋钢, 等. 强流氘氚聚变中子源HINEG设计研究[J]. 核科学与工程, 2016, 36(1):77-83. WU Yican, LIU Chao, SONG Gang, et al. Design study of high intensity D-T fusion neutron generator HINGE[J]. Nuclear Science and Engineering, 2016, 36(1):77-83.
22 谢仲生, 邓力. 中子输运理论数值计算方法[M]. 西安:西北工业大学出版社, 2005:303-345. XIE Zhongsheng, DENG Li. Neutron transport theory numerical method[M]. Xi'an:Northwestern Polytechnical University Press, 2005:303-345.
23 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.
24 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[J]. 核动力工程, 2014, 35(S2):83-86. DOI:10.13832/j.jnpe.2014.S2.0083. QIU Yishu, LIANG Jingang, WANG Kan. Preliminary study of sensitivity analysis based on iterated fission probability method[J]. Nuclear Power Engineering, 2014, 35(S2):83-86. DOI:10.13832/j.jnpe.2014.S2.0083.
25 刘勇, 曹良志, 吴宏春, 等. 基于经典微扰理论的特征值灵敏度和不确定性分析[J]. 原子能科学技术, 2015, 49(7):1247-1253. LIU Yong, CAO Liangzhi, WU Hongchun, et al. Eigenvalue sensitivity and uncertainty analysis based on classical perturbation theory[J]. Atomic Energy Science and Technology, 2015, 49(7):1247-1253.
26 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.
27 甘佺, 吴斌, 宋婧, 等. 基于参数的可视化裂变堆芯蒙特卡罗自动建模方法[J]. 核技术, 2016, 39(6):060501. DOI:10.11889/j.0253-3219.2016.hjs.39.060501. GAN Quan, WU Bin, SONG Jing, et al. Rapid parameter-based and visual Monte Carlo modeling method of fission reactor core[J]. Nuclear Techniques, 2016, 39(6):060501. DOI:10.11889/j.0253-3219.2016.hjs.39.060501.
28 Gan Q, Wu B, Yu S, et al. CAD-based hierarchical geometry conversion method for modeling of fission reactor cores[J]. Annals of Nuclear Energy, 2016, 94:369-375. DOI:10.1016/j.anucene.2016.03.013.
29 Pan X L, Wang J Q, Yuan R, et al. Biasing transition rate method based on direct MC simulation for probabilistic safety assessment[J]. Nuclear Science and Techniques, 2017, 28(7):91. DOI:10.1007/s41365-017-0255-2.

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Monte Carlo critical boron concentration search method based on adjoint flux

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