A supercritical water reactor accident analysis program (SPFR), based on Oka's conceptual design who work in Tokyo, has been verified. The impact about different correlations affecting the maximum temperature in hot channel including seed channels with upward and downward water and blanket channel also has been studied. In addition, loss of feedwater heating, partial loss of flow rate, pump seizure to the accident were analyzed with SPFR. And concluded:the impact that supercritical water heat transfer correlation to single-channel model for supercritical water reactor thermal calculation was not obvious; For supercritical water reactor accidents, loss of feed water heating, partial loss of flow rate, pump seizure, can be an effective mitigation by switching the turbine valves which can control the turbine inlet pressure.
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