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Annals of Nuclear Energy, 2021
Abstract The innovative technology of In-Vessel Retention – External Reactor Vessel Cooling (IVR-ERVC) is a mitigation countermeasure for severe accidents, which has been applied in the design of advanced pressurized water reactors. The validity of IVR-ERVC is restricted to boiling crisis and critical heat flux (CHF) of the reactor vessel lower head.
Daogang Lu +4 more
exaly +2 more sources
Abstract The innovative technology of In-Vessel Retention – External Reactor Vessel Cooling (IVR-ERVC) is a mitigation countermeasure for severe accidents, which has been applied in the design of advanced pressurized water reactors. The validity of IVR-ERVC is restricted to boiling crisis and critical heat flux (CHF) of the reactor vessel lower head.
Daogang Lu +4 more
exaly +2 more sources
Evaluation of an IVR-ERVC strategy for a high power reactor using MELCOR 2.1
Annals of Nuclear Energy, 2017Abstract The IVR-ERVC (In-Vessel Retention of molten corium through External Reactor Vessel Cooling) is an effective severe accident management strategy for reducing the possibility of a reactor containment failure by terminating the severe accident progress inside a reactor. However, the technical applicability and feasibility of the IVR-ERVC design
Kukhee Lim +3 more
openaire +1 more source
A theoretical and experimental study on subcooled flow boiling under passive IVR-ERVC conditions
Annals of Nuclear Energy, 2020Abstract External reactor vessel cooling (ERVC) strategy has been used in China advanced passive nuclear power plant. For this concept, it is very important to remove the decay heat through two phase natural circulation flow between reactor pressure vessel (RPV) wall and insulation.
Fan Wang +3 more
openaire +1 more source
Two-phase pressure gradient through a curved channel in case of IVR-ERVC
Nuclear Engineering and Design, 2019Abstract In-Vessel Retention (IVR) of corium through External Reactor Vessel Cooling (ERVC) is an ongoing technique for the extraction of heat out of the reactor pressure vessel (RPV). The efficiency of heat transfer and critical heat flux (CHF) are dependent on the optimal design of the external flow channel.
Rasool Urfa +3 more
exaly +2 more sources
Critical Heat Flux Experiments for IVR-ERVC Strategy Under the Pool Boiling Condition
Volume 7B: Thermal-Hydraulics and Safety Analysis, 2022Abstract Heat transfer limit is one of the main concerns of IVR-ERVC strategy. When the liquid level in the system is so low that natural circulation cannot be formed, the coolant near the outer surface of the reactor pressure vessel lower head is in the pool boiling state.
Gang Wang +3 more
exaly +2 more sources
CFD simulation on critical heat flux of flow boiling in IVR-ERVC of a nuclear reactor
Nuclear Engineering and Design, 2016Abstract The effectiveness of in-vessel retention (IVR) by external reactor vessel cooling (ERVC) strongly depends on the critical heat flux (CHF). As long as the local CHF does not exceed the local heat flux, the lower head of the pressure vessel can be cooled sufficiently to prevent from failure.
Xiang Zhang +4 more
openaire +1 more source
An experimental study on natural circulation flow characteristics under passive IVR-ERVC conditions
Annals of Nuclear Energy, 2019Abstract In vessel retention (IVR) of molten core debris via water cooling at the external surface of the reactor vessel is an important severe accident management feature of advanced passive plants. During postulated severe accidents, the heat generated by the molten debris relocated to the lower head of reactor pressure vessel needs to be removed ...
Fan Wang +3 more
openaire +1 more source
Experimental study of IVR-ERVC CHF limits for CAP1400
Progress in Nuclear EnergyJinquan Yan +6 more
exaly +2 more sources
A critical heat flux model for IVR-ERVC application based on the experimental observation
Annals of Nuclear EnergyWang Gang +5 more
exaly +2 more sources