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舰船核动力装置非能动余热排出系统运行特性
引用本文:彭军,于雷.舰船核动力装置非能动余热排出系统运行特性[J].舰船科学技术,2012,34(7):64-67,95.
作者姓名:彭军  于雷
作者单位:海军工程大学,湖北武汉,430033
摘    要:用RELAP5/MOD3.2安全分析程序对某型舰船核动力装置非能动余热排出系统进行数学建模,并用实际装置的试验结果进行校核验证。重点分析了自然循环工况下蒸汽发生器U型管内冷却剂倒流特性对非能动余热排出系统运行特性的影响。结果表明:舰船核动力装置发生全部电源丧失事故时,蒸汽发生器二次侧非能动余热排出系统能正常投入运行,但蒸汽发生器U型管内冷却剂会发生倒流,降低了一回路主系统的自然循环能力。

关 键 词:非能动余热排出系统  蒸汽发生器  自然循环  RELAP5/MOD3.2

Research on the passive residual heat removal system operating characteristic of marine nuclear power plant
PENG Jun , YU Lei.Research on the passive residual heat removal system operating characteristic of marine nuclear power plant[J].Ship Science and Technology,2012,34(7):64-67,95.
Authors:PENG Jun  YU Lei
Institution:(Naval University of Engineering,Wuhan 430033,China)
Abstract:This paper simulate the passive residual heat removal system(PRHRS) of a type of marine nuclear power plant with RELAP5 / MOD3.2 code,which was verified the test results by the actual device. Analyses the reverse flow characteristic in the inverted U-tubes of the steam generator(SG) under natural circulation.The results show that when marine nuclear power plant loss of offsite power,the PRHRS of the secondary side of steam generator start up,but the coolant may reverse flow in the inverted U-tubes of the steam generator(SG),which reduce the natural circulation in primary loop system heat removal ability.
Keywords:passive residual heat removal system  steam generator  natural circulation  RELAP5 / MOD3  2
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