ROSA/LSTF test and RELAP5 code analyses on primary feed-and-bleed operation during total loss-of-feedwater transient of PWR
Sign Up to like & getrecommendations! Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2019.05.021
Abstract: Abstract An experiment was conducted using the rig of safety assessment/large-scale test facility (ROSA/LSTF), which simulated the primary feed-and-bleed operation during a total loss-of-feedwater transient of a pressurized water reactor. The primary feed-and-bleed operation included… read more here.
Keywords: feed bleed; test; lstf test; bleed operation ... See more keywords
Uncertainty analysis of ROSA/LSTF test by RELAP5 code and PKL counterpart test concerning PWR hot leg break LOCAs
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2018.05.005
Abstract: Abstract An experiment was conducted for the OECD/NEA ROSA-2 Project using the large-scale test facility (LSTF), which simulated a 17% hot leg intermediate-break loss-of-coolant accident in a pressurized water reactor (PWR). In the LSTF test,… read more here.
Keywords: hot leg; lstf test; test; uncertainty analysis ... See more keywords
ROSA/LSTF test and RELAP5 code analyses on PWR 1% vessel upper head small-break LOCA with accident management measure based on core exit temperature
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Technology"
DOI: 10.1016/j.net.2018.08.004
Abstract: Abstract An experiment was performed using the large-scale test facility (LSTF), which simulated a 1% vessel upper head small-break loss-of-coolant accident with an accident management (AM) measure under an assumption of total-failure of high-pressure injection… read more here.
Keywords: temperature; measure; upper head; lstf test ... See more keywords