Results 1 to 10 of about 114,871,075 (252)

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

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

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

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

Enhancement of Downward-Facing Saturated Boiling Heat Transfer by the Cold Spray Technique

open access: yesNuclear Engineering and Technology, 2017
In-vessel retention by passive external reactor vessel cooling under severe accident conditions is a viable approach for retention of radioactive core melt within the reactor vessel.
Faruk A. Sohag   +6 more
doaj   +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  

Structural assessment of reactor pressure vessel under multi-layered corium formation conditions

open access: yesNuclear Engineering and Technology, 2015
External reactor vessel cooling (ERVC) for in-vessel retention (IVR) has been considered one of the most useful strategies to mitigate severe accidents.
Tae Hyun Kim   +2 more
doaj   +1 more source

3D modelling of drug-coated balloons for the treatment of calcified superficial femoral arteries.

open access: yesPLoS ONE, 2021
Background/objectivesDrug-coated balloon therapy for diseased superficial femoral arteries remains controversial. Despite its clinical relevance, only a few computational studies based on simplistic two-dimensional models have been proposed to ...
Monika Colombo   +5 more
doaj   +1 more source

Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions

open access: yesScience and Technology of Nuclear Installations, 2022
In-vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants.
Shilei Han   +3 more
doaj   +1 more source

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