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Volume 34 Issue 4
Mar.  2025
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LUO Feng, ZHOU Tao, CHENG Wan-xu, SU Zi-wei, CHEN Juan. Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR[J]. Nuclear Power Engineering, 2013, 34(4): 100-105.
Citation: LUO Feng, ZHOU Tao, CHENG Wan-xu, SU Zi-wei, CHEN Juan. Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR[J]. Nuclear Power Engineering, 2013, 34(4): 100-105.

Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR

  • Received Date: 2012-05-04
  • Rev Recd Date: 2012-08-20
  • Available Online: 2025-03-08
  • Taking the Super LWR concept proposed by Japanese as the background,relevant mathematical and physical calculation models are built,and the effect of coast-down time of primary pump,scram delay and ratio of density coefficient on the maximum cladding surface temperature(MCST) is evaluated.The results show that: after the transient of partial loss of reactor coolant flow,due to the pump seize and reactor scram,the maximum cladding temperature increases quickly at first and then declines rapidly;extending the coast-down time of primary pump can delay the reduction in the flow of coolant,thereby delaying the increasing of maximum cladding temperature;scram delay is the shorter,thereby better slow down the maximum cladding temperature;Ratio of density coefficient affects the maximum cladding temperature changes a little.Visibly,the coast-down time of primary pump or the scram delay can be a significant impact on the safety performance of the core.

     

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