Three-Dimensional Pin-by-pin Transient Analysis for PWR-Core

被引：0
|
作者：
Qin J. [1 ]
Li Y. [1 ]
Wang K. [2 ]
Wu H. [1 ]
Cao L. [1 ]
机构：
[1] Xi’an Jiaotong University, Xi’an
[2] Nuclear and Radiation Safety Center, Beijing
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 06期
关键词：
NECP-Bamboo; Pin-by-pin; PWR; Transient analysis;
D O I：
10.13832/j.jnpe.2023.06.0032
中图分类号：
学科分类号：
摘要：
In order to ensure the safety of nuclear reactor in transient process, it is necessary to carry out three-dimensional transient analysis of the whole core to obtain the power distribution of fuel rods concerned in the safety analysis. In this paper, a theoretical model of the pin-by-pin neutronic-thermohydraulic coupling transient analysis for PWR-core is established: the three-dimensional pin-by-pin spatio-temporal neutron dynamics calculation of PWR-core is realized by fully implicit backward difference method and exponential function expansion nodal method; the multi-channel model of cell scale is used to calculate the thermal feedback of three-dimensional full core pin-by-pin; the Picard iteration is used to realize the iterative calculation of neutronic-thermohydraulic tight coupling; using the parallel technology of message passing interface (MPI) and the unified spatial domain decomposition method, the parallel calculation of neutronic-thermohydraulic coupling transient process is realized. Based on the theoretical model, the corresponding code called Bamboo-Transient 2.0 was developed and verified by the benchmark and multi-assemblies questions, and it was then applied to the transient analysis for commercial PWRs. The results show that the pin-by-pin transient analysis code has more fine results than that of the traditional coarse-mesh diffusion code based on assembly homogenization, and it can reduce the deviation of power distribution of pin-cell. Meanwhile, it can provide the distribution of state parameters at cell scale, which can directly meet the requirements of safety analysis. © 2023 Atomic Energy Press. All rights reserved.
引用
收藏
页码：32 / 38
页数：6
相关论文
共 13 条
  • [1] LI Y Z, HE T, LIANG B N, Et al., Development and verification of PWR-core nuclear design code system NECP-Bamboo: Part III: Bamboo-transient, Nuclear Engineering and Design, 359
  • [2] GARCIA-HERRANZ N, CUERVO D, SABATER A, Et al., Multiscale neutronics/thermal-hydraulics coupling with COBAYA4 code for Pin-by-pin PWR transient analysis, Nuclear Engineering and Design, 321, pp. 38-47, (2017)
  • [3] GRAHN A, KLIEM S, ROHDE U., Coupling of the 3D neutron kinetic core model DYN3D with the CFD software ANSYS-CFX, Annals of Nuclear Energy, 84, pp. 197-203, (2015)
  • [4] LEE D, KOZLOWSKI T, DOWNAR T J., Multi-group SP3 approximation for simulation of a three-dimensional PWR rod ejection accident[J], Annals of Nuclear Energy, 77, pp. 94-100, (2015)
  • [5] TADA K, YAMAMOTO A, YAMANE Y, Et al., Applicability of the diffusion and simplified P3 theories for pin-by-pin geometry of BWR, Journal of Nuclear Science and Technology, 45, 10, pp. 997-1008, (2008)
  • [6] (2018)
  • [7] 47, pp. 664-667, (2013)
  • [8] WAND YQ, RABITI C, PALMIOTTI G., Parallelization of the red-black algorithm on solving the second-order PN transport equation with the hybrid finite element method, Transactions of American Nuclear Society, 105, pp. 319-321, (2011)
  • [9] LI Y Z, ZHANG B, HE Q M, Et al., Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part I Bamboo-Lattice, Nuclear Engineering and Design, 335, pp. 432-440, (2018)
  • [10] YANG W, WU H C, LI Y Z, Et al., Development and verification of PWR-core fuel management calculation code system NECP-Bamboo: Part II Bamboo-Core, Nuclear Engineering and Design, 337, pp. 279-290, (2018)
12