Research on the Conversion Method of Critical Calculation Model for Fuel Storage Rack

Ma Jiancong; Wang Yiqi; Liu Shichang; Yu Miao; Shao Zeng

doi:10.13832/j.jnpe.2024.S2.0206

Volume 45 Issue S2

Jan. 2025

Turn off MathJax

Article Contents

Abstract

References

Article Navigation > Nuclear Power Engineering > 2024 > 45(S2): 206-213

Ma Jiancong, Wang Yiqi, Liu Shichang, Yu Miao, Shao Zeng. Research on the Conversion Method of Critical Calculation Model for Fuel Storage Rack[J]. Nuclear Power Engineering, 2024, 45(S2): 206-213. doi: 10.13832/j.jnpe.2024.S2.0206

Citation:

Ma Jiancong, Wang Yiqi, Liu Shichang, Yu Miao, Shao Zeng. Research on the Conversion Method of Critical Calculation Model for Fuel Storage Rack[J]. Nuclear Power Engineering, 2024, 45(S2): 206-213. doi: 10.13832/j.jnpe.2024.S2.0206

Citation:

PDF( 4456 KB)

Research on the Conversion Method of Critical Calculation Model for Fuel Storage Rack

doi: 10.13832/j.jnpe.2024.S2.0206

1.
North China Electric Power University, Beijing, 102206, China
2.
China Nuclear Power Engineering Co, Ltd., Beijing, 100840, China

Received Date: 2024-06-21
Rev Recd Date: 2024-09-13
Publish Date: 2025-01-06

Abstract

Abstract

To improve the modeling efficiency and accuracy of RMC (Reactor MonteCarlo Code) in critical calculations for spent fuel storage racks, and to promote the application of autonomous Monte Carlo code in critical analysis of spent fuel storage racks, a conversion code for the input files of the Monte Carlo code MONK and RMC has been developed. For the description cards of geometry, hole, material, control and source of MONK code, the corresponding reading code was developed based on python language. The code could read the card calculation input file of MONK 3D Monte Carlo code and generate the input file of RMC 3D Monte Carlo code. After comparison, the generated RMC input file model is consistent with MONK input file model in terms of geometry, material, source terms and computational control conditions. The effective multiplication factors before and after conversion are calculated respectively, and the effective multiplication factors are the same within the allowable error range. The results show that the code meets the requirements for the conversion of critical calculation code input cards for spent fuel storage racks, which can improve the efficiency and accuracy of modeling spent fuel storage racks, and also verifies the correctness of applying RMC to critical calculations for spent fuel storage racks.
- Criticality calculation for spent fuel storage rack,
- Conversion code,
- MONK,
- RMC

FullText(HTML)

References(13)

References

[1]	徐鹏. 燃料贮存格架的临界安全分析研究[J]. 核科学与工程,2010, 30(S1): 187-195.
[2]	石红. 乏核燃料贮存格架地震及组件跌落事故安全分析[D]. 北京: 北京化工大学,2012.
[3]	韩向臻,攸国顺,潘昕怿,等. 基于SCALE的压水堆乏燃料贮存水池临界安全分析[J]. 核电子学与探测技术,2016, 36(4): 408-411. doi: 10.3969/j.issn.0258-0934.2016.04.014
[4]	LONG D, RICHARDS S, SMITH P N, et al. MONK10: A Monte Carlo code for criticality analysis[C]//Proceedings of 2015 International Conference on Nuclear Criticality Safety. Charlotte: ICNC, 2015: 13.
[5]	梁志. MONK-8B程序的开发研究[C]//全面建设小康社会: 中国科技工作者的历史责任——中国科协2003年学术年会论文集(上). 沈阳: 中国测绘学会,2003: 1.
[6]	TALAMO A, GOHAR Y, ALIBERTI G, et al. MCNPX, MONK, and ERANOS analyses of the YALINA Booster subcritical assembly[J]. Nuclear Engineering and Design, 2011, 241(5): 1606-1615. doi: 10.1016/j.nucengdes.2011.03.006
[7]	王璠,朱庆福,夏兆东,等. 硝酸浓度对临界安全的影响研究[J]. 原子能科学技术,2024, 58(1): 144-148. doi: 10.7538/yzk.2023.youxian.0161
[8]	李航,周琦,朱庆福. MOX燃料贮存水池核临界安全分析[J]. 原子能科学技术,2018, 52(8): 1388-1392. doi: 10.7538/yzk.2017.youxian.0771
[9]	李航,周琦,朱庆福. 乏燃料溶解器燃料棒随机分布建模方法[J]. 核动力工程,2017, 38(1): 29-31. doi: 10.13832/j.jnpe.2017.01.0029.
[10]	RICHARDS S D, BAKER C M J, BIRD A J, et al. MONK and MCBEND: current status and recent developments[J]. Annals of Nuclear Energy, 2015, 82: 63-73. doi: 10.1016/j.anucene.2014.07.054
[11]	RICHARDS S, DOBSON G, FRY T, et al. Recent developments to the MONK Monte Carlo code for criticality safety and reactor physics analyses[C]//Proceedings of the ICNC 2019-11th International Conference on Nuclear Criticality Safety. Paris: ICNC, 2019.
[12]	TALAMO A, GOHAR Y, KONDEV F, et al. Modeling of the YALINA booster facility by the Monte Carlo code MONK[C]//Proceedings of the 8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators. Pocatello: Argonne National Lab, 2007.
[13]	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

Relative Articles

[1]	Shen Pengfei, Wang Kan, Liu Zhaoyuan, Liang Jingang, Liu Shichang. Extended Development and Application of CAD-based Transport in RMC[J]. Nuclear Power Engineering, 2024, 45(S2): 55-62. doi: 10.13832/j.jnpe.2024.S2.0055
[2]	An Nan, Wang Wu, Wang Kan. Implementation and Optimization of Function Expansion Tallies Based on Track Length Estimation Method in RMC[J]. Nuclear Power Engineering, 2024, 45(5): 78-84. doi: 10.13832/j.jnpe.2024.05.0078
[3]	Mei Zhen, Sun Fujiang, Zhu Gang, Yu Ying, Chen Juan, Lu You. Study on Design and Safety Analysis of Spent Fuel Storage Grid for Marine Nuclear Power Platform[J]. Nuclear Power Engineering, 2021, 42(3): 177-183. doi: 10.13832/j.jnpe.2021.03.0177
[4]	Ou Jianlei, Yuan Zhimin, Wu Wei, Luo Wenguang, Liao Jiatao. Development of Underwater Lifting Tool for Spent Fuel Storage Rack in Nuclear Power Plants[J]. Nuclear Power Engineering, 2021, 42(4): 182-185. doi: 10.13832/j.jnpe.2021.04.0182
[5]	Wu Shijian, Shang Ertao, Liu Pan, Gao Chen, Xu Xiao, Nie Zhaoyu. Multi-DOF Nonlinear Seismic Analysis of Spent Fuel Storage Grid Based on Super-Element Technology[J]. Nuclear Power Engineering, 2020, 41(1): 79-82. doi: 10.13832/j.jnpe.2020.01.0079
[6]	Cheng Wei, Wang Lei, Hu Jianhua, Wang Zhiming, Zhang Peng, Ji Dapeng. Research and Application of Spent Fuel Storage Racks Positioning Test Method Based on Machine Vision[J]. Nuclear Power Engineering, 2020, 41(6): 198-201.
[7]	Pan Qingquan, Wang Kan. Energy Biased Variance Reduction Method for Deep Penetration Problems[J]. Nuclear Power Engineering, 2020, 41(1): 1-6. doi: 10.13832/j.jnpe.2020.01.0001
[8]	Luo Wenguang, Ou Jianle. Development of Underwater Decontamination Device for Spent Fuel Storage Rack in Nuclear Power Plants[J]. Nuclear Power Engineering, 2019, 40(5): 146-149.
[9]	Li Wanlin, Yu Ganglin, Wang Kan, Li Yaodong. Research on Preventing Xenon Oscillation in Monte Carlo Burnup Calculation Based on RMC[J]. Nuclear Power Engineering, 2018, 39(2): 133-136. doi: 10.13832/j.jnpe.2018.02.0133
[10]	Guo Xiaoyu, Shang Xiaotong, Qiu Yishu, Cheng Quan, Song Jing, Huang Shanfang, Wang Kan. RMC Solutions to Kinetic Cases of C5G7-TD Benchmark[J]. Nuclear Power Engineering, 2018, 39(2): 129-132. doi: 10.13832/j.jnpe.2018.02.0129
[11]	Mo Huaisen, Yuan Chengyu, Tan Jingyao. Independent Development of a New-Style Spent Fuel Storage Rack[J]. Nuclear Power Engineering, 2016, 37(2): 116-121. doi: 10.13832/j.jnpe.2016.02.0116
[12]	Qiu Yishu, Liang Jingang, Yu Jiankai, Wang Kan. Parallel Strategies and Verification of Sensitivity Analysis Function of RMC Code[J]. Nuclear Power Engineering, 2015, 36(3): 152-156. doi: 10.13832/j.jnpe.2015.03.0152
[13]	Yang Haifeng, Huo Xiaodong, Yi Xuan, SHao Zeng. Criticality Safety Design for High Density Spent Fuel Storage Rack[J]. Nuclear Power Engineering, 2014, 35(S2): 167-169. doi: 10.13832/j.jnpe.2014.S2.0167
[14]	Zhao Jun, Han Song, Su Genghua, SHi Xiuan, Cai Dechang. Effect of Neutron Absorber Layout Scheme for Spent Fuel Storage on Critical Safety[J]. Nuclear Power Engineering, 2014, 35(S2): 164-166. doi: 10.13832/j.jnpe.2014.S2.0164
[15]	Liang Jingang, Qiu Yishu, Wang Kan, Chai Xiaoming, Qiang Shenglong. Research of Full Core Burnup Calculations Based on Tally Data Decomposition in RMC[J]. Nuclear Power Engineering, 2014, 35(S2): 231-234. doi: 10.13832/j.jnpe.2014.S2.0231
[16]	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
[17]	Liang Jingang, Wang Kan, Yu Ganglin, She Ding, Chai Xiaoming, Qiang Shenglong, Yao Dong. Research on Tally Data Decomposition Algorithms Based on Reactor Monte Carlo Code RMC[J]. Nuclear Power Engineering, 2014, 35(4): 142-146. doi: 10.13832/j.jnpe.2014.04.0142
[18]	Tang Xiao, Liang Jingang, Wang Kan, Ge Panhe, Li Wanlin. Verification on Criticality Calculation of RMC with BEAVRS Full-Core Benchmark[J]. Nuclear Power Engineering, 2014, 35(S2): 235-238. doi: 10.13832/j.jnpe.2014.S2.0235
[19]	QIU Yishu, SHE Ding, FAN Xiao, WANG Kan, LI Zeguang, LIANG Jingang. Analysis of Full-Core Calculation of RMC[J]. Nuclear Power Engineering, 2013, 34(S1): 1-4,23.
[20]	SHE Ding, WANG Kan, YU Ganglin. Development of Burnup Calculation Function in Reactor Monte Carlo Code RMC[J]. Nuclear Power Engineering, 2012, 33(3): 1-5,11.