Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1851875 | Nuclear Science and Techniques | 2006 | 7 Pages |
Abstract
The technology of passive safety is the current trend among safety systems in nuclear power plant. Passive 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 transient characteristics of all startup modes of the PRHRS. However, the quantitative description is poor during the initial stages of the transition process when water hammer occurs.
Keywords
Related Topics
Physical Sciences and Engineering
Physics and Astronomy
Nuclear and High Energy Physics
Authors
XIAO Ze-Jun, QIU Sui-Zheng, ZHUO Wen-Bin, FAN Pu, CHEN Bing-De, JIA Dou-Nan,