Results 31 to 40 of about 6,570 (105)

Reliability Assessment of Reactor AP1000 Passive ERVC System

open access: yes, 2017
As the safety requirements level of nuclear power plant is gradually improving, more and more passive systems are used in the advanced type reactors.
Chen Ying   +4 more
core   +1 more source

Margin for In-Vessel Retention in the APR1400 - VESTA and SCDAP/RELAP5-3D Analyses [PDF]

open access: yes, 2004
If cooling is inadequate during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident.
Rempe, Joy, Knudson, D.
core   +1 more source

A Novel Point Estimate Procedure for IVR Calculations in Core-Molten Severe Accident

open access: yes, 2010
In-Vessel Retention (IVR) of core melt is a key severe accident management strategy adopted by operating nuclear power plants and advanced light water reactors (ALWRs), AP600, AP1000 etc.
Yapei Zhang   +3 more
core   +1 more source

Potential for AP600 in-vessel retention through ex-vessel flooding [PDF]

open access: yes, 1997
External reactor vessel cooling (ERVC) is a new severe accident management strategy that involves flooding the reactor cavity to submerge the reactor vessel in an attempt to cool core debris that has relocated to the vessel lower head.
Thinnes, G. L.   +4 more
core   +1 more source

Prediction of critical heat flux on surface under boiling in case of IVR-ERVC by using CFD simulation

open access: yesIOP Conference Series: Materials Science and Engineering, 2019
Abstract The efficacy of in-vessel through external reactor vessel cooling (IVR-ERVC) is strongly correlated with the critical heat flux (CHF) on the lower head of reactor pressure vessel (RPV). The high limit of CHF prevents the RPV from failure by extracting much heat out of the vessel through the circulation of working fluid in ...
Rasool Urfa   +4 more
openaire   +1 more source

An assessment methodology for in-vessel corium retention by external reactor vessel cooling during severe accidents in PWRs

open access: yes, 2001
A consistent probabilistic approach is proposed to evaluate the feasibility of in-vessel retention of the molten corium through external reactor vessel cooling (IVR-ERVC) during severe accidents of pressurized water reactors (PWRs).
Baek, Won Pil   +3 more
core   +1 more source

Effect of the heat transfer liquid fin on critical heat flux enhancement under ERVC condition

open access: yes, 2020
Several critical heat flux (CHF) enhancement methods for in-vessel retention through external reactor vessel cooling (IVR-ERVC) have been researched. However, they have some limitations for practical applications.
Heo, Hyo, Bang, In Cheol, Lee, Min Ho
core   +1 more source

Experimental study of advanced IVR-ERVC strategy with liquid metal coolant

open access: yes, 2014
In this work, the boiling tests were conducted to confirm the heat transfer characteristics with small-scaled IVR-ERVC facility. When the liquid metal was flooded surrounding the reactor vessel, the effective heat transfer area could be enlarged.
Park, SD, Bang, In Cheol
core  

The Analytical and Experimental Research of In-Vessel Corium Retention in CPR1000

open access: yes, 2010
The analytical and experiment research of In-Vessel Corium Retention (IVR) in the Chinese Pressurized-water Reactor 1000 MWe (CPR1000) are introduced. The IVR research consists of preliminary phase and detailed phase.
Xing Chen   +3 more
core   +1 more source

Heat Removal Characteristics of IVR-ERVC Cooling System using Gallium Liquid Metal

open access: yes, 2015
The present work ultimately aims to develop the IVR-ERVC (In-Vessel Retention through External Reactor Vessel Cooling) system with enough thermal margin adopting liquid metal coolant as the severe accident mitigation system even for high power reactor ...
Heo, Hyo   +2 more
core  

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