| 基于MOOSE框架的五方程两相流分析程序开发 |
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| 引用本文： | 邓超群,向烽瑞,贺亚男,牛钰航,巫英伟,田文喜,秋穗正,苏光辉.基于MOOSE框架的五方程两相流分析程序开发[J].原子能科学技术,2021,55(8):1429-1439. |
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| 作者姓名： | 邓超群 向烽瑞 贺亚男 牛钰航 巫英伟 田文喜 秋穗正 苏光辉 |
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| 作者单位： | 西安交通大学 动力工程多相流国家重点实验室，陕西 西安710049；中国核动力研究设计院 核反应堆系统设计技术重点实验室，四川 成都610213 |
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| 摘 要： | 基于多物理场耦合框架MOOSE，采用五方程两相流模型开发了模块化程序ZEBRA，实现了高阶时间、空间离散格式两相流动传热问题的求解。采用Bartolomei开展的垂直圆管过冷沸腾实验对ZEBRA进行验证，在不同热流密度、质量流密度、压力工况下，将程序计算值与实验值进行了数值验证和计算分析。结果表明：ZEBRA中五方程模型预测值与实验值符合良好，沸腾起始点和空泡份额的预测合理，表明ZEBRA初步具备了处理两相流问题的能力。
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| 关 键 词： | MOOSE 五方程两相流 流动换热 |
Development and Validation of Fuel Rod Performance Transient Analysis Code Based on MOOSE Platform |
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| DENG Chaoqun,XIANG Fengrui,HE Yanan,NIU Yuhang,WU Yingwei,TIAN Wenxi,QIU Suizheng,SU Guanghui.Development and Validation of Fuel Rod Performance Transient Analysis Code Based on MOOSE Platform[J].Atomic Energy Science and Technology,2021,55(8):1429-1439. |
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| Authors: | DENG Chaoqun XIANG Fengrui HE Yanan NIU Yuhang WU Yingwei TIAN Wenxi QIU Suizheng SU Guanghui |
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| Affiliation: | State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China; Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China |
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| Abstract: | As the core component of the reactor system, the performance of fuel rod is very important for the safe operation of the reactor. It is of great significance to accurately predict the behavior change of fuel rod under transient accident for reactor safety analysis. Fuel behavior models applicable to reactivity insertion accident (RIA) and loss of coolant accident (LOCA) were implemented in fuel rod performance analysis code BEEs, which was developed based upon the finite element platform MOOSE, and validations of separate models against experimental data were conducted. Integral analyses of CABRI RIA Na 2 and NRU LOCA MT4 tests were conducted to validate the modeling capacity of BEEs during RIA and LOCA, respectively. The results show that the overall modeling capacity of BEEs code for PWR fuel rod during transient accidents can be verified, predictions by BEEs code of fuel temperature, mechanical deformation and internal pressure in integral analyses are reasonable, which indicates the extended models of elastic-plasticity, high-temperature creep, phase transition, high-temperature oxidation and failure criteria of cladding are applicable to the performance analysis of fuel rod under transient accidents further. |
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| Keywords: | fuel performance loss of coolant accident reactivity insertion accident MOOSE platform BEEs code |
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