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The development and verification of thermal-hydraulic code on passive residual heat removal system of Chinese advanced PWR 被引量:1
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作者 XIAO Ze-Jun QIU Sui-Zheng +3 位作者 ZHUO Wen-Bin FAN Pu CHEN Bing-De JIA Dou-Nan 《Nuclear Science and Techniques》 SCIE CAS CSCD 2006年第5期301-307,共7页
The technology of passive safety is the current trend among safety systems in nuclear power plant. Pas- sive residual heat removal system (PRHRS), a major part of passive safety systems of Chinese advanced PWR, is a n... The technology of passive safety is the current trend among safety systems in nuclear power plant. Pas- sive residual heat removal system (PRHRS), a major part of passive safety systems of Chinese advanced PWR, is a novel design with three-fold natural circulation. On the basis of reasonable physics and mathematics models, MI- TAP-PRHRS code was developed to analyze steady and transient characteristics of the PRHRS. The calculation and analysis show that the code simulates steady characteristics of the PRHRS very well, and it is able to simulate tran- sient characteristics of all startup modes of the PRHRS. However, the quantitative description is poor during the ini- tial stages of the transition process when water hammer occurs. 展开更多
关键词 压水反应堆 剩余热除热系统 循环液法 核技术
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