Results 1 to 10 of about 1,532 (134)

Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2023
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters in lower head, which may threat the reliability of ...
Shihao Wu   +6 more
doaj   +4 more sources

Structural Integrity Evaluation of a Reactor Cavity during a Steam Explosion for External Reactor Vessel Cooling [PDF]

open access: yesEnergies, 2021
Nuclear power is a major source of electricity in the international community. However, a significant problem with nuclear power is that, if a severe nuclear accident occurs, radiation may leak and cause great damage.
Sang-Hyun Park   +2 more
doaj   +2 more sources

Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment [PDF]

open access: yesFrontiers in Energy Research, 2022
Due to large uncertainty, the effectiveness of in-vessel retention (IVR) with external reactor vessel cooling (ERVC) for high-power reactors cannot be fully demonstrated during the transient process. To optimize the current IVR-ERVC strategy, the concept
Peng Chen   +4 more
doaj   +4 more sources

Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate

open access: yesNuclear Engineering and Technology, 2022
This paper presents a numerical investigation of two-phase natural circulation flows established when external reactor vessel cooling is applied to a severe accident of the APR1400 reactor for the in-vessel retention of the core melt.
Min Seop Song   +3 more
doaj   +3 more sources

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

open access: yesNuclear Engineering and Technology, 2015
Background: A numerical simulation was carried out to investigate the difference between internal and external heat-flux distributions at the reactor vessel wall under in-vessel retention through external reactor vessel cooling (IVR-ERVC). Methods: Total
Jaehoon Jung   +3 more
doaj   +3 more sources

Modeling corium pool stratification and focusing effect in APR1400 using a multiphase CFD framework [PDF]

open access: yesScientific Reports
Accurately predicting molten corium behavior is critical for assessing severe accident scenarios in nuclear reactors, particularly under In-Vessel Corium Retention with Reactor Vessel External Cooling (IVCR-RVEC) strategies.
Kamran Mahboob   +2 more
doaj   +2 more sources

Numerical simulation on in-vessel molten corium behavior with external vessel cooling using smoothed particle hydrodynamics

open access: yesNuclear Engineering and Technology
The in-vessel retention through external reactor vessel cooling (IVR-ERVC) strategy is a key management strategy for early termination of a nuclear severe accident that can threaten the integrity of the reactor vessel.
Tae Hoon Lee   +5 more
doaj   +3 more sources

Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition

open access: yesNuclear Engineering and Technology, 2016
A visualization test of the fuel–coolant interaction in the Test for Real cOrium Interaction with water (TROI) test facility was carried out. To experimentally simulate the In-Vessel corium Retention (IVR)- External Reactor Vessel Cooling (ERVC ...
Young Su Na   +3 more
doaj   +2 more sources

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

open access: yesScience and Technology of Nuclear Installations, 2022
In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants.
Shilei Han   +3 more
doaj   +1 more source

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