Results 11 to 20 of about 2,961,144 (192)

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   +4 more sources

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

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

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   +4 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   +4 more sources

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

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   +3 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

Study of nuclear reactor external vessel passive cooling using computational fluid dynamics [PDF]

open access: yesNuclear Engineering and Design, 2021
Nuclear energy has recently re-gained support as a reliable source of carbon-free electricity. However, the safety of nuclear plants is still questioned, particularly in the wake of the tragic events in Fukushima. In response to this, the adoption of passive safety systems, providing cooling to the plant even in the absence of any active power, has ...
Colombo, M., Fairweather, M.
openaire   +4 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

Experimental Study on Influence of External Pressure Vessel Cooling Parameters on Critical Heat Flux [PDF]

open access: yesYuanzineng kexue jishu
In-vessel retention (IVR) of molten material, as one of the most important mitigation measures for serious accidents, can effectively prevent the leakage of molten material from the core to the outside of the pressure vessel, resulting in the release of ...
ZHANG Zhen1, 2, XIONG Wanyu2, XING Dianchuan2, ZAN Yuanfeng2, WANG Guangjin2, CHEN Deqi1, 3, , XU Jianjun2
doaj   +2 more sources

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