Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5
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DOI: 10.1016/j.anucene.2018.12.019
Abstract: Abstract The RELAP5/MOD3.3 code was used to simulate a Main Steam Line Break (MSLB) Loss of Coolant Accident (LOCA) on a Generation III type Reactor with passive safety features. The MSLB is a hypothetical multi-failure… read more here.
Keywords: large break; break loca; uncertainty; break ... See more keywords
Effect of emergency core cooling system flow reduction on channel temperature during recirculation phase of large break loss-of-coolant accident at Wolsong unit 1
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2017.03.007
Abstract: Abstract The feasibility of cooling in a pressurized heavy water reactor after a large break loss-of-coolant accident has been analyzed using Multidimensional Analysis of Reactor Safety-KINS Standard code during the recirculation phase. Through evaluation of… read more here.
Keywords: recirculation; break loss; temperature; large break ... See more keywords
Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident
Sign Up to like & getrecommendations! Published in 2018 at "Energies"
DOI: 10.3390/en11123324
Abstract: In this study, we aim to conduct structural analyses of cladding materials, such as silicon carbide and zircaloy-4, during a Large-Break Loss-of-Coolant Accident. The safety margin is the key consideration regarding the performance of the… read more here.
Keywords: silicon carbide; cladding materials; carbide zircaloy; safety ... See more keywords