Neutronics Influence Research on Axial Grid of PWR Fuel Assembly

Huang Xing; Wan Chenghui; Li Yunzhao; Wu Hongchun; Gu Weiquan; Cai Guangming; Xu Jialong

doi:10.13832/j.jnpe.2022.01.0052

Volume 43 Issue 1

Feb. 2022

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2022 > 43(1): 52-56

Huang Xing, Wan Chenghui, Li Yunzhao, Wu Hongchun, Gu Weiquan, Cai Guangming, Xu Jialong. Neutronics Influence Research on Axial Grid of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(1): 52-56. doi: 10.13832/j.jnpe.2022.01.0052

Citation:

Huang Xing, Wan Chenghui, Li Yunzhao, Wu Hongchun, Gu Weiquan, Cai Guangming, Xu Jialong. Neutronics Influence Research on Axial Grid of PWR Fuel Assembly[J]. Nuclear Power Engineering, 2022, 43(1): 52-56. doi: 10.13832/j.jnpe.2022.01.0052

Citation:

PDF( 6857 KB)

Neutronics Influence Research on Axial Grid of PWR Fuel Assembly

doi: 10.13832/j.jnpe.2022.01.0052

1.
School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an, 710049, China
2.
Nuclear Energy Creative Power Co., Ltd., Xi’an, 710077, China
3.
Fujian Fuqing Nuclear Power Co., Ltd., Fuqing, Fujian, 350318, China

Received Date: 2021-01-04
Accepted Date: 2021-12-21
Rev Recd Date: 2021-08-20
Publish Date: 2022-02-01

Abstract

Abstract

The heterogeneous modeling method and homogenous modeling method have been respectively proposed for the axial grids based on the advanced fuel-management code for PWR named Bamboo-C. Based on these two different modeling methods for axial grids, modeling analysis for the fuel assemblies of M310 reactor in Fuqing Nuclear Power Plant is carried out. By comparing with the measured data of the reactor core, the effects of two different modeling methods on the critical boron concentration, axial power distribution and axial power offset are tested. The numerical results show that the axial heterogeneous modeling method of PWR fuel assembly can significantly improve the calculation accuracy of the key physical parameters of the reactor core.
- Axial grids,
- Neutronics effects,
- Heterogeneous modeling method,
- Homogenous modeling method

FullText(HTML)

References(15)

References

[1]	姚波,向文欣,王鹏,等. AFA3G LE燃料组件的结构特点和设计论证[J]. 核动力工程,2015, 36(S1): 40-43.
[2]	杨晓东. AFA 3G及其它高性能燃料组件[J]. 原子能科学技术,2003, 37(S1): 15-20.
[3]	陈军,周有新,李石磊,等. 跨间交混格架对EPR堆芯DNBR裕量的影响[J]. 原子能科学技术,2013, 47(2): 249-253. doi: 10.7538/yzk.2013.47.02.0249
[4]	段蓉, 于超, 林俊, 等. 燃料组件格架对堆芯核设计参数的影响分析[C]//第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议. 西安: 西安交通大学, 2020
[5]	GIRIEUD P, DAUDIN L, GARAT C, et al. Science Version 2: the most recent capabilities of the Framatome 3-D nuclear code package[C]//Conference: 9. International Conference on Nuclear Engineering. Nice Acropolis, France: Societe Francaise d'Energie Nucleaire, 2001.
[6]	万承辉, 李云召, 郑友琦, 等. 压水堆燃料管理软件Bamboo-C研发及工业确认[C]//第十八届反应堆数值计算与粒子输运学术会议暨2020年反应堆物理会议. 西安: 西安交通大学, 2020.
[7]	ZU T J, XU J L, TANG Y Q, et al. NECP-Atlas: a new nuclear data processing code[J]. Annals of Nuclear Energy, 2019, 123: 153-161. doi: 10.1016/j.anucene.2018.09.016
[8]	LIU Z Y, HE Q M, ZU T J, et al. The pseudo-resonant-nuclide subgroup method based global-local self-shielding calculation scheme[J]. Journal of Nuclear Science and Technology, 2018, 55(2): 217-228. doi: 10.1080/00223131.2017.1394232
[9]	TIAN C, ZHENG Y Q, LI Y Z, et al. Neutron transport study based on assembly modular ray tracing MOC method[J]. Nuclear Power Engineering, 2015, 36(3): 157-161.
[10]	PUSA M, LEPPÄNEN J. Computing the matrix exponential in Burnup calculations[J]. Nuclear Science and Engineering, 2010, 164(2): 140-150. doi: 10.13182/NSE09-14
[11]	SMITH K S. Assembly homogenization techniques for light water reactor analysis[J]. Progress in Nuclear Energy, 1986, 17(3): 303-335. doi: 10.1016/0149-1970(86)90035-1
[12]	RHODES J, SMITH K, XU Z W. CASMO-5 energy release per fission mode[C]//CASMO5 - Advanced Lattice Physics Code for Light Water Reactors. Interlaken Switzerland, 2008.
[13]	DOWNAR T, XU Y, SEKER V. Theory manual for the PARCS kinetics core simulator module[R]. Michigan: University of Michigan, 2010.
[14]	JOO H G, YOON J I, BAEK S G. Multigroup pin power reconstruction with two-dimensional source expansion and corner flux discontinuity[J]. Annals of Nuclear Energy, 2009, 36(1): 85-97. doi: 10.1016/j.anucene.2008.10.003
[15]	吴宏春. 核反应堆物理[M]. 北京: 中国原子能出版社, 2014: 112-113.