Analysis on LOCA for CSR1000
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.07.026
Abstract: Abstract In CSR1000 (Chinese Supercritical Water Cooled Reactor 1000), based on the existing SCAC-CSR1000 code, by incorporating break flow model and passive safety system, CSR1000-DP02 code for LOCA analysis is developed. 50% hot leg break… read more here.
Keywords: loca csr1000; loca; analysis loca; csr1000 ... See more keywords
Parametric explorative study of DEMO galleries pressurization in case of ex-vessel LOCA
Sign Up to like & getrecommendations! Published in 2017 at "Fusion Engineering and Design"
DOI: 10.1016/j.fusengdes.2017.03.120
Abstract: Abstract Radioactive toxins confinement is a main safety function for fusion power plants, hence the importance of confinement design parameters optimization. Moving from this perspective, two Loss of Coolant Accidents (LOCAs) were analyzed: loss of… read more here.
Keywords: parametric explorative; galleries pressurization; demo; loca ... See more keywords
Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software
Sign Up to like & getrecommendations! Published in 2021 at "Progress in Nuclear Energy"
DOI: 10.1016/j.pnucene.2021.103949
Abstract: Abstract The behavior of Emergency Core Cooling System (ECCS) in an Advanced Pressurized Reactor 1400 (APR) during the early stage of Loss of Coolant Accident (LOCA), was analyzed by using Flownex software. The LOCA has… read more here.
Keywords: system; loca; core cooling; core ... See more keywords