K Kim, BJ Kim, HS Choi, SK Moon, CH Song - Nuclear Engineering and …, 2017 - Elsevier
If fuel rods are ballooned or rearranged during the reflood phase of a large break loss-of- coolant accident (LBLOCA) in a pressurized-water reactor (PWR), the transient heat transfer …
W Liu, P Wu, M Gui, J Shan, Z Li - Annals of Nuclear Energy, 2024 - Elsevier
This experimental study delves into the impact of inlet injection velocity, inlet subcooling, and linear power density on the quench front propagation during reflooding in 5x5 rod …
SH Hong, S Kang, J Kim, JK Park, SK Moon - Nuclear Engineering and …, 2018 - Elsevier
Reflood experiments at elevated pressures for small and medium break loss-of-coolant accidents were performed to investigate the influence of fuel deformation on the peak …
L'un des accidents de dimensionnement d'un réacteur à eau pressurisée est l'Accident de Perte de Réfrigérant Primaire (APRP). L'évènement initiateur d'un tel accident est une …
Z Hózer, I Nagy, M Kunstár, P Szabó, N Vér… - … Engineering and Design, 2017 - Elsevier
The CODEX-COOL experimental series was carried out in order to evaluate the effect of ballooning and pellet relocation in hexagonal bundles on the coolability of fuel rods after a …
JM Yoo, BJ Yun, HY Yoon, JJ Jeong - Nuclear Engineering and Design, 2021 - Elsevier
When a flow blockage is formed by fuel swelling in the reflood phase of a large-break loss-of- coolant-accident (LOCA) in a pressurized water reactor (PWR), flow separation and …
BJ Kim, JR Kim, K Kim, SK Moon - … of the Korean Nuclear Society Spring …, 2015 - kns.org
In the 1980s, various experimental programs were carried out for the coolability of an assembly containing a partial blockage in a group of ballooned fuel rods under LOCA …
SH Hong, JK Park, YJ Youn, HS Choi, SK Moon - Power (kW), 2017 - kns.org
Depending on the size of break on the cold legs and its phenomenology on the reactor despondence, the postulated LOCA (Loss Of coolant Accident) can be categorized into LB …
J Kim, JK Park, S Cho, YJ Youn, HS Choi, SH Hong… - 2016 - kns.org
For a loss-of-coolant accident (LOCA) conditions in a pressurized-water reactor (PWR), the coolant level decreases and then fuel core is uncovered. The cladding temperature of …