Results 161 to 170 of about 2,961,144 (192)
Some of the next articles are maybe not open access.

Loop analysis of a natural circulation two-phase flow under an external reactor vessel cooling

International Communications in Heat and Mass Transfer, 2008
Under ERVC (External Reactor Vessel Cooling) conditions in a severe accident, a natural circulation two-phase flow is driven and a decay heat from the reactor vessel wall can be removed for an integrity of a reactor vessel wall. In this study, to estimate a natural circulation mass flow rate and to analyze the major factor determining the natural ...
Kwang Soon Ha, Rae Joon Park
exaly   +2 more sources

One-dimensional experiments of a natural circulation two-phase flow under an external reactor vessel cooling

International Communications in Heat and Mass Transfer, 2008
During a severe accident in a nuclear power plant, a decay heat from a molten corium should be removed to maintain an integrity of the reactor vessel. This feasible strategy can be achieved by a External Reactor Vessel Cooling (ERVC) which requires a coolant to be circulated sufficiently between the reactor vessel and its insulation.
Kwang Soon Ha, Rae Joon Park
exaly   +2 more sources

Flow analyses using RELAP5/MOD3 code for OPR1000 under the external reactor vessel cooling

open access: yesAnnals of Nuclear Energy, 2006
Abstract External reactor vessel cooling (ERVC) is considered as one of the most promising severe accident management strategies for an in-vessel corium retention (IVR). Heat removal capacity and water availability at the vessel outer surface can be key factors determining the success of ERVC measures.
Kang, KH Kang, Kyoung-Ho   +4 more
openaire   +3 more sources

CHF enhancement by vessel coating for external reactor vessel cooling

Nuclear Engineering and Design, 2006
Abstract In-vessel retention (IVR) is a key severe accident management (SAM) strategy that has been adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). One viable means for IVR is the method of external reactor vessel cooling (ERVC) by flooding the reactor cavity during a severe accident.
J. Yang   +5 more
openaire   +1 more source

Structural integrity assessment of the reactor pressure vessel under the external reactor vessel cooling condition

Nuclear Engineering and Design, 1999
Since the suggestion of external reactor vessel cooling (ERVC), the effects of melting and cooling on the response of structural integrity of the reactor pressure vessel (RPV) under core melting accident conditions have been investigated. To investigate the initial behavior of RPV lower head and the effects of analysis conditions on the structural ...
Jong Sung Kim, Tae Eun Jin
openaire   +1 more source

External cooling of a reactor vessel under severe accident conditions

Nuclear Engineering and Design, 1993
Abstract The TMI-2 accident demonstrated that a significant quantity of molten core debris could drain into the lower plenum during a severe accident. For such conditions, the Individual Plant Examinations (IPEs) and severe accident management evaluations, consider the possibility that water could not be injected to the RCS. However, depending on the
Robert E. Henry, Hans K. Fauske
openaire   +1 more source

An experimental study of hypervapotron structure in external reactor vessel cooling

Nuclear Engineering and Design, 2016
Abstract In vessel retention (IVR) is one of the key strategies for many advanced LWR designs to mitigate postulated severe accidents. The success of IVR substantially relies on external reactor vessel cooling (ERVC) by which the decay heat is removed from the melt core in the reactor vessel lower head.
Yufeng Zhao   +4 more
openaire   +1 more source

Simulation of external reactor vessel cooling in a lumped-parameter code

Kerntechnik, 2013
Abstract In the course of a severe accident in a nuclear power plant the integrity of the reactor vessel may be preserved by External Reactor Vessel Cooling (ERVC). By flooding the cavity surrounding the reactor vessel the decay heat is removed from molten core material through the vessel wall to water at the submerged vessel surface. In
U. Schittek, M. K. Koch
openaire   +1 more source

Analysis of External Cooling of the Reactor Vessel During Severe Accidents

Nuclear Technology, 2002
An analysis is presented of the integral behavior of the external cooling of a reactor vessel by natural circulation during a severe accident to investigate the feasibility of the in-vessel retention strategy for a high-power reactor by using the RELAP5/MOD3 computer code.
Jin Ho Song, Sang Baik Kim, Hee Dong Kim
openaire   +1 more source

Home - About - Disclaimer - Privacy