CEFR非对称运行工况的研究

林超, 冯预恒, 周志伟

林超, 冯预恒, 周志伟. CEFR非对称运行工况的研究[J]. 原子能科学技术, 2016, 50(6): 1021-1026. DOI: 10.7538/yzk.2016.50.06.1021
引用本文: 林超, 冯预恒, 周志伟. CEFR非对称运行工况的研究[J]. 原子能科学技术, 2016, 50(6): 1021-1026. DOI: 10.7538/yzk.2016.50.06.1021
LIN Chao, FENG Yu-heng, ZHOU Zhi-wei. Study on Unsymmetrical Operating Condition of CEFR[J]. Atomic Energy Science and Technology, 2016, 50(6): 1021-1026. DOI: 10.7538/yzk.2016.50.06.1021
Citation: LIN Chao, FENG Yu-heng, ZHOU Zhi-wei. Study on Unsymmetrical Operating Condition of CEFR[J]. Atomic Energy Science and Technology, 2016, 50(6): 1021-1026. DOI: 10.7538/yzk.2016.50.06.1021

CEFR非对称运行工况的研究

Study on Unsymmetrical Operating Condition of CEFR

  • 摘要: 为研究中国实验快堆(CEFR)非对称运行工况,通过快堆系统安全分析程序OASIS及堆芯子通道分析程序COBRA对CEFR单环路运行时堆内的温度以及流量进行了计算。结果表明,CEFR在单环路运行,完好环路一、二次钠泵转速为500 r/min,且事故环路一次钠泵逆止阀开启时,堆芯最多开启在14%的功率水平,以确保反应堆处于安全状态。

     

    Abstract: In order to study the unsymmetrical operating condition of China Experimental Fast Reactor (CEFR), the temperature and flow rate of CEFR operating with only single loop were calculated with the system analysis code OASIS and the sub-channel code COBRA. The results show that when CEFR is operating with only single loop while the rotating speeds of the primary sodium pump in that loop and the sodium pump in the corresponding secondary loop are both at 500 r/min and the check valve of the other primary pump of the failed loop is open, the max power of the core should be set at 14% in order to ensure that the reactor is safe.

     

  • [1] 李文宏,陈道龙,鲍扬民,等. 中国实验快堆最终安全分析报告:第五章[R]. 北京:中国原子能科学研究院,2008.
    [2] 钱鸿涛. OASIS程序说明书[R]. 北京:中国原子能科学研究院,2012.
    [3] 郝老迷,金德圭,谢晖. THAS-PCI反应堆热工水力微机程序[R]. 北京:中国原子能科学研究院,1990.
    [4] ROWE D S. COBRA-Ⅲ-C: A digital computer program for steady state and transient thermal-hydraulic of rod bundle nuclear fuel elements, BNWL-1695[R]. Washington, USA: Battelle Pacific Northwest Laboratory, 1973.
    [5] WHEELER C L. COBRA-Ⅳ-1: An interim version of COBRA for thermal-hydraulic analysis of rod bundle elements and cores, BNWL-1962[R]. [S. l.]: [s.n.], 1976.
    [6] 杨福昌. 平衡态氧化铀堆芯稳态热工设计[R]. 北京:中国原子能科学研究院,2002.
计量
  • 文章访问数:  177
  • HTML全文浏览量:  0
  • PDF下载量:  1124
  • 被引次数: 0
出版历程
  • 刊出日期:  2016-06-19

目录

    /

    返回文章
    返回