Development and verification of fuel assembly bowing model in software package PCM

Li Jinggang; Wang Chao; Chen Jun; Peng Jinghan

doi:10.11884/HPLPB202234.210378

Volume 34 Issue 2

Jan. 2022

Turn off MathJax

Article Contents

Article Navigation > High Power Laser and Particle Beams > 2022 > 34(2): 026004

Li Jinggang, Wang Chao, Chen Jun, et al. Development and verification of fuel assembly bowing model in software package PCM[J]. High Power Laser and Particle Beams, 2022, 34: 026004. doi: 10.11884/HPLPB202234.210378

Citation:

Li Jinggang, Wang Chao, Chen Jun, et al. Development and verification of fuel assembly bowing model in software package PCM[J]. High Power Laser and Particle Beams, 2022, 34: 026004. doi: 10.11884/HPLPB202234.210378

Citation:

PDF( 992 KB)

Development and verification of fuel assembly bowing model in software package PCM

doi: 10.11884/HPLPB202234.210378

China Nuclear Power Technology Research Institute Co., Ltd., Shenzhen 518000, China

Received Date: 2021-08-30
Accepted Date: 2021-12-06
Rev Recd Date: 2021-10-21

Available Online: 2021-12-11

Publish Date: 2022-01-11

Abstract

Abstract

The fuel assemblies bow with different stresses in the PWR reactor core and this phenomenon can significantly affect the local neutron moderation in the reactor core. Based on the CGN’s in-house software package PCM, which is composed of the fuel assembly neutron cross section software PINE and the core design software COCO, this study developed a specific model for fuel assembly bowing to analyze the impact on local power distribution, and compared the results with that of the Monto Carlo code JMCT. The study shows that the results of fuel assembly bowing model in PCM have good consistency with those of JMCT, and that PCM is valid in fuel assembly bowing analysis. The fuel assembly bowing has a significant impact on core local power distribution. This phenomenon shall be specially considered in the PWR reactor design.
- fuel assembly bowing,
- core power distribution,
- PCM,
- water gap,
- neutron cross section

FullText(HTML)

References(10)

References

[1]	李伟才, 肖忠. 压水堆燃料组件弯曲变形机理及规避措施[J]. 核动力工程, 2008, 29(2):55-57. (Li Weicai, Xiao Zhong. Mechanism fuel assembly bowing preventive measures[J]. Nuclear Power Engineering, 2008, 29(2): 55-57
[2]	Franzen A. Evaluation of fuel assembly bow penalty peaking factors for Ringhals 3 – Based on a cycle specific core water gap distribution[D]. Uppsala Universitet, 2017.
[3]	Rochman D, Mala P, Ferroukhi H, et al. Bowing effects on power and burn-up distributions for simplified full PWR and BWR cores[C]//International Conference on Mathematics & Computational Methods Applied to Nuclear Science & Engineering. 2017.
[4]	Chionis D, Dokhane A, Belblidia L, et al. Development and verification of a methodology for neutron noise response to fuel assembly vibrations[J]. Annals of Nuclear Energy, 2020, 147: 17669-107683.
[5]	Yamamoto A, Endo T, Nagano H, et al. A simple treatment of increased gap due to fuel assembly bowing through correction of cross sections[J]. Journal of Nuclear Science and Technology, 2019.
[6]	Franceschini F, Fetterman R, Little D. Modification of the ANC nodal code for analysis of PWR assembly bow[C]//Proc PHYSOR. 2008.
[7]	Fetterman R, Franceschini F. Analysis of PWR assembly bow[C]//Proc PHYSOR. 2008.
[8]	卢皓亮, 莫锟, 李文淮, 等. 自主化堆芯三维核设计软件COCO研发[J]. 原子能科学技术, 2013, 47(s1):327-330. (Lu Haoliang, Mo Kun, Li Wenhuai, et al. Development of self-reliant three-dimensional core nuclear design code COCO[J]. Atomic Energy Science and Technology, 2013, 47(s1): 327-330
[9]	卢皓亮, 陈俊, 王军令, 等. 自主化堆芯核设计软件COCO验证与确认[J]. 原子能科学技术, 2017, 51(8):1460-1463. (Lu Haoliang, Chen Jun, Wang Junling, et al. Verification and validation of self-reliant core nuclear design code COCO[J]. Atomic Energy Science and Technology, 2017, 51(8): 1460-1463
[10]	邓力, 雷炜, 李刚, 等. 高分辨率粒子输运MC软件JMCT开发[J]. 核动力工程, 2014, 35(S2):221-223. (Deng Li, Lei Wei, Li Gang, et al. Development of high resolution particle transport Monte Carlo code JMCT[J]. Nuclear Power Engineering, 2014, 35(S2): 221-223