Results 11 to 20 of about 423,593 (300)

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. Advanced and existing light water reactors (LWRs) are considering ERVC as an accident management strategy for in ...
Rempe, J. L.   +4 more
openaire   +3 more sources

Methodology of safety evaluation of In-Vessel Retention

open access: yes, 2020
International Seminar "In-vessel retention: outcomes of IVMR project'', IRSN, Jan 2020, Juan Les Pins (FR ...
Fichot, Florian   +3 more
openaire   +4 more sources

In-vessel tritium retention and removal in ITER [PDF]

open access: yesJournal of Nuclear Materials, 1999
Abstract Tritium retention inside the vacuum vessel has emerged as a potentially serious constraint in the operation of the International Thermonuclear Experimental Reactor (ITER). In this paper we review recent tokamak and laboratory data on hydrogen, deuterium and tritium retention for materials and conditions which are of direct relevance to the ...
Federici, G.   +18 more
openaire   +2 more sources

Study on the influences of RPV deformation on CHF under IVR conditions

open access: yesFrontiers in Energy Research, 2023
After the reactor core melt, the thermal impact of high temperature molten mixture to the lower head of reactor pressure vessel (RPV) will cause the shape change of cooling channel constituted by reactor pressure vessel outer surface and other supporting
Shuang Wen   +13 more
doaj   +1 more source

Numerical Study on the Corium Pool Heat Transfer With OpenFOAM

open access: yesFrontiers in Energy Research, 2020
In order to ensure the successful implementation of in-vessel retention strategy to terminate molten corium pool evolution, it is necessary to evaluate the heat flux distribution on the lower head wall of reactor pressure vessel.
Zhiguo Xi   +9 more
doaj   +1 more source

IVR design and review of advanced NPPs in China: Issues and perspectives

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2021
The In-Vessel Retention (IVR) is an attractive strategy which could avoid the failure of Reactor Pressure Vessel (RPV) and consequent phenomenon in severe accident of nuclear power plants (NPPs). Most advanced NPPs designed in China adopt the IVR measure,
Yang Zhiyi   +5 more
doaj   +1 more source

Research on Optimized Design of In-Vessel Retention–External Reactor Vessel Cooling Strategy and Negative Effect Assessment

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   +1 more source

Experimental discussion on fragmentation mechanism of molten oxide discharged into a sodium pool

open access: yesMechanical Engineering Journal, 2016
In a probable scenario for core disruptive accidents of Sodium-cooled Fast Reactors (SFRs), it is foreseen that molten core material would be discharged into lower sodium plenums through control rod guide tubes.
Ken-ichi MATSUBA   +6 more
doaj   +1 more source

Analysis of critical points of the In-Vessel Retention safety evaluation

open access: yes, 2020
International audienceIn-Vessel Retention (IVR) strategy for nuclear reactors in case of a Severe Accident (SA) intends to stabilize and retain the corium in the vessel by using the vessel wall as a heat exchanger with an external water loop.
Carénini, Laure, Fichot, Florian
core   +1 more source

Different Heat Transfer Modes of Heavy Metallic Layer in IVR Strategy

open access: yesYuanzineng kexue jishu, 2022
There might be a three-layer molten pool configuration with a heavy metallic layer at the bottom in the stratified molten pool configuration. Because of the decay heat in the heavy metallic layer and the relatively low critical heat flux (CHF) at the ...
LI Zongyang;CHANG Huajian;CHEN Lian;HAN Kun;FANG Fangfang
doaj  

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