Takeshi Takeda
Uncertainty Analysis of ROSALSTF Test on Pressurized Water Reactor Cold Leg SmallBreak LossofCoolant Accident without Scram
82 - 90
2019
13
2
International Journal of Nuclear and Quantum Engineering
https://publications.waset.org/pdf/10010005
https://publications.waset.org/vol/146
World Academy of Science, Engineering and Technology
The author conducted posttest analysis with the RELAP5MOD3.3 code for an experiment using the ROSALSTF (rig of safety assessmentlargescale test facility) that simulated a 1 cold leg smallbreak lossofcoolant accident under the failure of scram in a pressurized water reactor. The LSTF test assumed total failure of highpressure injection system of emergency core cooling system. In the LSTF test, natural circulation contributed to maintain core cooling effect for a relatively long time until core uncovery occurred. The posttest analysis result confirmed inadequate prediction of the primary coolant distribution. The author created the phenomena identification and ranking table (PIRT) for each component. The author investigated the influences of uncertain parameters determined by the PIRT on the cladding surface temperature at a certain time during core uncovery within the defined uncertain ranges.
Open Science Index 146, 2019