强激光与粒子束, 2015, 27 (9): 096003, 网络出版: 2015-11-30  

压力管嵌入式燃料部件入口堵流事故多尺度热工模拟

Multi-scale thermal engineering simulation on the inlet flow blockage accident of pressure tube embedded fuel component
作者单位
中国工程物理研究院 核物理与化学研究所, 四川 绵阳 621900
摘要
压力管嵌入式燃料部件内冷却剂管道间不存在横向交混,若燃料辐照肿胀或碎片进入冷却管道内,容易引发堵流事故,造成局部冷却条件恶化,使燃料烧毁。考虑到次临界能源包层流动路径长、方向弯曲等特点,针对入口堵流事故提出一种多尺度热工模拟方法,通过RELAP5程序给计算流体力学(CFD)软件提供边界条件,对核功率密度最高的燃料部件入口处第一排单根流道部分堵塞和全部堵塞工况进行数值模拟,分析事故条件下燃料热工安全特性。结果表明:第一排单根流道部分堵塞时燃料温度仍满足安全限值,而全部堵塞时峰值温度将超过燃料相变温度限值。
Abstract
Due to that no cross flow exists in pressure tube embedded plate-type fuel component, the flow blockage accidents are apt to occur under some conditions, i.e., irradiation swelling of fuel or fragments entering into the cooling channel. The accidents may deteriorate the cooling condition and result in the phenomenon of departuring from nucleate boiling. Considering the special flow characteristics of the long and curved paths in fusion-fission hybrid energy reactor blanket, a simulation method with multi-scale thermal model is proposed. The boundary conditions calculated by RELAP5 code are provided to computational fluid dynamics (CFD) code. The thermal characteristics of the fuel component which has the largest deposited power density under partial and total flow blockage accidents are simulated. The results indicate that the fuel temperature still meet thermal safety criterion when the single cooling channel partially blocked. The peak temperature of fuel component will exceed the limit of phase-transition temperature when totally blocked.
参考文献

[1] 宋磊, 郭赟, 曾和义, 等. 板状燃料组件入口堵流事故下流场和温度场的瞬态数值计算[J]. 核动力工程, 2014, 35(3): 6-10.

    Song Lei, Guo Yun, Zeng Heyi, et al. Numerical analysis on transient flow and temperature field during inlet flow blockage accident of plate-type assembly. Nuclear Power Engineering, 2014, 35(3): 6-10

[2] 李茂生, 师学明, 刘荣, 等. 次临界能源堆物理设计进展[J]. 强激光与粒子束, 2014, 26: 100203.

    Li Maosheng, Shi Xueming, Liu Rong, et al. Progress in physics design of fusion-fission hybrid energy reactor. High Power Laser and Particle Beams, 2014, 26: 100203

[3] Adorni M, Bousbia-Salah A, Hamidouche T, et al. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core[J]. Annals of Nuclear Energy, 2005, 32(15): 1679-1692.

[4] Lu Q, Qiu S, Su G H. Flow blockage analysis of a channel in a typical material test reactor core[J]. Nuclear Engineering & Design, 2009, 239(1):45-50.

[5] Salama A, El-Morshedy S. CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core[J]. Annals of Nuclear Energy, 2012, 41(3):26-39.

[6] 周喆, 汪俊, 张慧敏. 次临界能源堆安全性研究[J]. 原子能科学技术, 2015, 49(1): 106-110.

    Zhou Ze, Wang Jun, Zhang Huimin. Study on safety of subcritical nuclear power reactor. Atomic Energy Science and Technology, 2015, 49(1): 106-110

[7] 郭海兵. 次临界能源堆包层热工水力设计及物理-热工耦合研究[D]. 北京:清华大学, 2012: 60-65.

    Guo Haibing. Thermal-hydraulic design and coupled analysis with neutronics of subcritical energy blanket. Beijing: Tsinghua University, 2012: 60-65

[8] 曾和荣, 黄洪文,刘志勇, 等. ITER驱动次临界包层总体结构概念设计[J]. 强激光与粒子束, 2015, 27:016014.

    Zeng Herong, Huang Hongwen, Liu Zhiyong, et al. Whole structure conceptual design of subcritical blanket driven by ITER. High Power Laser and Particle Beams, 2015, 27: 016014

[9] 喻章程, 解横. 聚变-裂变混合堆冷却剂布置优化及堆外自然循环分析[J]. 核聚变与等离子体物理, 2013, 33(2):166-174. Yu Zhangcheng, Xie Heng. Optimization of coolant arrangement for fusion-fission hybrid reactor and analysis of ex-core nature circulation. Nuclear Fusion and Plasma Physics, 2013, 33(2):166-174

蒋钢, 刘耀光, 黄洪文, 郭海兵, 马纪敏. 压力管嵌入式燃料部件入口堵流事故多尺度热工模拟[J]. 强激光与粒子束, 2015, 27(9): 096003. Jiang Gang, Liu Yaoguang, Huang Hongwen, Guo Haibing, Ma Jimin. Multi-scale thermal engineering simulation on the inlet flow blockage accident of pressure tube embedded fuel component[J]. High Power Laser and Particle Beams, 2015, 27(9): 096003.

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