Results 71 to 80 of about 6,570 (105)

Safety research of IVR-ERVC for advanced water cooled reactor

Energy, 2018
Abstract After Fukushima accident, more and more attention has been paid on severe accident analysis. As an important severe accident mitigation strategy applied to advanced light water reactor for in-vessel retention (IVR), an important method is external reactor vessel cooling (ERVC).
Xiaojing Liu
exaly   +3 more sources

Analysis on CHF deviation caused by geometry of the heater blocks in a validation test of IVR-ERVC technology

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
exaly   +2 more sources

Mechanistic CHF model development based on the liquid sublayer dryout model for flow boiling phenomena under IVR-ERVC conditions

Annals of Nuclear Energy
In this work a mechanistic critical heat flux (CHF) model was developed based on the liquid sublayer dryout (LSD) model, designed to predict CHF in downward-facing flow boiling conditions, particularly the operational environment of In-Vessel Retention ...
Min Suk Lee, Yong Hoon Jeong
exaly   +3 more sources

Critical Heat Flux Experiments for IVR-ERVC Strategy Under the Pool Boiling Condition

Volume 7B: Thermal-Hydraulics and Safety Analysis, 2022
Abstract 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, Bo Kuang, Yihai He, Pengfei Liu   +3 more
exaly   +2 more sources

Two-phase pressure gradient through a curved channel in case of IVR-ERVC

Nuclear Engineering and Design, 2019
Abstract 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.
Daogang Lu
exaly   +2 more sources

Investigation of the pressure vessel lower head potential failure under IVR-ERVC condition during a severe accident scenario in APR1400 reactors

Nuclear Engineering and Design, 2021
Abstract In the event of a core meltdown in a high-power reactor, the integrity of the reactor pressure vessel is presumably protected by severe accident mitigation systems such as in-vessel retention external reactor vessel cooling (IVR-ERVC). However, in the late phase of the accident, two possible locations on the RPV are prone to failure: the ...
Muritala Alade Amidu, Yacine Addad, Jeong Ik Lee, Dong Hoon Kam, Yong Hoon Jeong   +4 more
openaire   +2 more sources

Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR-ERVC Condition

Journal of Nuclear Engineering and Radiation Science, 2015
The main failure mechanism of in-vessel corium retention through external reactor vessel cooling (IVR-ERVC) happens when the local heat flux through reactor pressure vessel (PRV) wall exceeds the critical heat flux (CHF). High local heat flux in the molten pool is usually caused by the metallic layer focusing effect due to stratification. In this paper,
Xi Wang, Xu Cheng
exaly   +2 more sources

Detailed evaluation of natural circulation mass flow rate in the annular gap between the outer reactor vessel wall and insulation under IVR-ERVC

Annals of Nuclear Energy, 2016
Abstract IVR (In-Vessel corium Retention) through ERVC (External Reactor Vessel Cooling) is known to be an effective means for maintaining the reactor vessel integrity during a severe accident in a nuclear power plant. Detailed simulations of a two phase natural circulation flow in the reactor cavity of an APR (Advanced Power Reactor) 1400 and ...
Rae-Joon Park, Kwang-Soon Ha
exaly   +2 more sources

Research progress on boiling heat transfer of nanofluids with emphasis on IVR-ERVC strategy

Thermal Science and Engineering Progress, 2023
Zixiang Su, Shenghui Liu
exaly   +2 more sources

Experimental study of IVR-ERVC CHF limits for CAP1400

Progress in Nuclear Energy
Huang Zhang, Chenglong Wang
exaly   +2 more sources