Results 11 to 20 of about 1,560 (162)

Transient heat transfer and crust evolution during debris bed melting process in the hypothetical severe accident of HPR1000

open access: yesNuclear Engineering and Technology, 2023
In the late in-vessel phase of a nuclear reactor severe accident, the internal heat transfer and crust evolution during the debris bed melting process have important effects on the thermal load distribution along the vessel wall, and further affect the ...
Chao Lv   +4 more
doaj   +1 more source

High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

open access: yesFrontiers in Energy Research, 2022
During a severe accident in a nuclear reactor, the molten core—or corium—may be relocated into the reactor vessel’s lower plenum in case of core support plate failure.
Jules Delacroix   +2 more
doaj   +1 more source

Modeling of IVR and Sensitivity Analysis of Cavity Injection System of a 1000MWe Advanced PWR

open access: yesMehran University Research Journal of Engineering and Technology, 2022
In-Vessel Retention (IVR) is one of the primary technique to mitigate severe accidents. This enables retaining the corium inside the Reactor Pressure Vessel (RPV) through external cooling.
Muhammad Usman   +3 more
doaj   +1 more source

Studies on Key Effect Factors of Natural Circulation Characteristics for Advanced PWR Reactor Cavity Flooding System

open access: yesScience and Technology of Nuclear Installations, 2020
In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), different kinds of severe accident mitigation strategies have been proposed.
Dekui Zhan   +4 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

Can a nanofluid enhance the critical heat flux if the recirculating coolant contains debris?

open access: yesNuclear Engineering and Technology, 2022
In-vessel corium retention (IVR) during external reactor vessel cooling (ERVC) is a key severe accident management strategy adopted in advanced nuclear power plants. The injection of nanofluids has been regarded as a means of enhancing CHF when using the
Jihoon Han, Giju Nam, Hyungdae Kim
doaj   +1 more source

External Reactor Vessel Cooling Evaluation for Severe Accident Mitigation in NPP Krško

open access: yesJournal of Energy : Energija, 2022
The In-Vessel corium Retention (IVR) through the External Reactor Vessel Cooling (ERVC) is mean for maintaining the reactor vessel integrity during a severe accident, by cooling and retaining the molten material inside the reactor vessel. By doing this, significant portion of severe accident negative phenomena connected with reactor vessel failure ...
Mihalina, Mario   +2 more
openaire   +3 more sources

Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2022
In this study, we investigated the characteristics of natural convection heat transfer of single-layer and two-layer corium pool in the elliptical lower head by the numerical method.
Y.P. Zhang   +6 more
doaj   +1 more source

APPLICATION OF UNCERTAINTY ANALYSIS TO MAAP4 ANALYSES FOR LEVEL 2 PRA PARAMETER IMPORTANCE DETERMINATION

open access: yesNuclear Engineering and Technology, 2013
MAAP4 is a computer code that can simulate the response of a light water reactor power plant during severe accident sequences, including actions taken as part of accident management.
KEVIN ROBERTS, ROBERT SANDERS
doaj   +1 more source

Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool [PDF]

open access: yesMechanical Sciences, 2018
The strategy denoted as in-vessel retention (IVR) is widely used in severe accident (SA) management by most advanced nuclear power plants. The essence of IVR mitigation is to provide long-term external water cooling in maintaining the reactor pressure
J. Mao   +10 more
doaj   +1 more source

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