Best estimate plus uncertainty analysis of a small‐break LOCA on an advanced Generation‐III pressurized water reactor
Sign Up to like & getrecommendations! Published in 2020 at "International Journal of Energy Research"
DOI: 10.1002/er.5920
Abstract: To improve the economy of nuclear power plants, a passively pressurized water reactor with additional 40% power output was developed based on AP1000 technologies. In this study, the RELAP5 code was used to model the… read more here.
Keywords: reactor; pressurized water; uncertainty; water reactor ... See more keywords
Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
Sign Up to like & getrecommendations! Published in 2017 at "Science and Technology of Nuclear Installations"
DOI: 10.1155/2017/4762709
Abstract: Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions. In reactor analysis, small… read more here.
Keywords: notrump code; analysis; small break; analysis small ... See more keywords
Uncertainty calculation in small break LOCA in the emergency core cooling system connected to the hot leg of Angra 2 nuclear power plant
Sign Up to like & getrecommendations! Published in 2018 at "International Journal of Nuclear Energy Science and Technology"
DOI: 10.1504/ijnest.2018.094284
Abstract: Owing to the occurrence of nuclear accidents, worldwide nuclear regulatory organisations included the analysis of accidents considered as design basis accidents - Loss of Coolant Accident (large and small-break, LBLOCA or SBLOCA) - in the… read more here.
Keywords: emergency core; cooling system; small break; angra nuclear ... See more keywords