Analysis of Primary Loop System of High-Order Fully-Implicit Nuclear Reactor Based on MOOSE Platform

被引：0

作者：

Niu Y. ^{[1
]}

He Y. ^{[1
]}

Wu Y. ^{[1
]}

Xiang F. ^{[1
]}

Deng C. ^{[1
]}

Yu Y. ^{[2
]}

Su G. ^{[1
]}

Qiu S. ^{[1
]}

Tian W. ^{[1
]}

Lu T. ^{[2
]}

机构：

[1] State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an

[2] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2021年 / 42卷 / 06期

关键词：

High-Order fully-implicit; MOOSE; System analysis;

D O I：

10.13832/j.jnpe.2021.06.0050

中图分类号：

学科分类号：

摘要：

Based on the multi-physics coupling platform MOOSE (Multiphysics Object Oriented Simulation Environment), the modular system safety analysis code, ZEBRA, was developed. The high-order and fully-implicit discrete format was presented to establish the nuclear reactor primary loop model. And the coupling calculation of nuclear reactor system including neutron diffusion, two-dimensional solid heat conduction, and one-dimensional fluid were also implemented. For the problem of flow and heat transfer in a single pipe, the ZEBRA code is coupled and verified, and the solution accuracy of first-order and second-order spatial discrete formats under steady-state conditions and Implicit-Euler, Crank-Nicolson and BDF2 schemes under transient conditions are compared, and the steady-state and power-reducing transient conditions of PWR loop system are simulated and analyzed. The results show that the high-order spatial discrete format has a higher accuracy, and the BDF2 time discrete format is in best agreement with the theoretical solution. The temperature, velocity, and pressure distribution of the PWR loop system are reasonable. The steady-state and transient calculation results are in good agreement with those of RELAP5. © 2021, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

引用

页码：50 / 57

页数：7

共 14 条

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