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广东台山核电站稳压器卸压箱热工设计方法
引用本文:宫爱成,张波,高亚甫.广东台山核电站稳压器卸压箱热工设计方法[J].动力工程,2012(7):577-580.
作者姓名:宫爱成  张波  高亚甫
作者单位:巾广核工程有限公司,深圳518124
摘    要:根据理想气体状态方程、质量守恒定律、能量守恒定律,假定热力平衡态卸压箱中为饱和蒸汽,推导了核电站稳压器卸压箱的容积设计方法,探讨了不同温度和压力限值对卸压箱容积设计的影响,以及如何确定水位控制范围,并对台山一期核电站的稳压器卸压箱和鼓泡管喷嘴处的热工参数进行了核算.结果表明:推导出的稳压器卸压箱的热工参数完全符合工程设计实际情况,为国内压水堆核电站稳压器卸压箱的热工设计提供了思路.

关 键 词:核电站  稳压器  卸压箱  热工设计  容积计算

Thermal Design and Calculation of Pressurizer Relief Tanks
Affiliation:GONG Ai cheng , ZHANG Bo , GAO Ya- fu (China Guangdong Nuclear Power Engineering Co. , Ltd. , Shenzhen 518124, China)
Abstract:Assuming that the steam in pressurizer relief tank (PRT) is in the saturated state under thermo dynamic equilibrium condition, and based on the state equation of ideal gas and the laws of conservation of mass and energy, a method for design and calculation of PRT capacity is proposed for nuclear power plants, while influence of temperature and pressure limit on the PRT capacity analyzed, including how to determine the control range of water level. The method has been verified with thermal parameters of PRT and sparger nozzle in Taishan Nuclear Power Plant Phase I. Results show that the thermal parameters ob- tained by the method are in good conformance with actual engineering requirements, which may therefore serve as a reference for thermal design of pressurizer relief tank for nuclear power plants.
Keywords:nuclear power plant  pressurizer  relief tank  thermal design  capacity calculation
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