Forced reflood modeling in a 2× 2 rod bundle with a 90% partially blocked region

M Hashemi-Tilehnoee, S Tashakor, SM Seyyedi… - Annals of Nuclear …, 2019 - Elsevier
Reflooding is a complicated thermal-hydraulic process in a loss of coolant accident (LOCA)
related to the nuclear reactor safety issues. Due to the physical nature of multi-scale behind …

Effect of a blockage length on the coolability during reflood in a 2× 2 rod bundle with a 90% partially blocked region

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 …

Experimental investigation of quench front propagation during reflooding in 5× 5 rod bundle channel with axial uniform power distribution

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 …

Reflood experiments at elevated pressures using intact and deformed rod bundles to simulate small and medium break loss-of-coolant accidents

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 …

Étude expérimentale du transfert paroi/fluide dans le cas d'un écoulement vertical vapeur/gouttes dans une géométrie tubulaire

JDP Carrillo - 2018 - theses.hal.science
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 …

Experimental investigation of the coolability of blocked hexagonal bundles

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 …

Improvement of the heat transfer enhancement model considering the droplet-wall heat transfer downstream of the flow blockage in the reflood phase

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 …

[PDF][PDF] Reflood Phenomena in a 5x5 Ballooned Rod Bundle

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 …

[PDF][PDF] Experiments on Reflood with Deformed Fuel Rods during SB-MB LOCA in PWR

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 …

[PDF][PDF] A Study of the Reflood Characteristics Under Small and Medium LOCA Using A 3x3 Heater Bundle

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 …