Results 1 to 10 of about 8,520 (102)

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

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   +7 more sources

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   +3 more sources

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   +2 more sources

Uncertainty analysis of molten corium In-Vessel Retention under External Reactor Vessel Cooling

open access: yesInternational Journal of Advanced Nuclear Reactor Design and Technology, 2023
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters in lower head, which may threat the reliability of ...
Shihao Wu   +6 more
doaj   +1 more source

Influence of an in-vessel debris bed on the heat load to a reactor vessel under an IVR condition

open access: yesNuclear Engineering and Technology, 2023
We measured the heat load to a reactor vessel with and without the in-vessel debris bed under an IVR-ERVC condition. Mass transfer methodology was adopted based on heat and mass transfer analogy to achieve high Ra′H of order ∼1015 with compact test rigs.
Joon-Soo Park   +2 more
doaj   +1 more source

Coupled Analysis of Heat Transfer in a Molten Pool With Three-Layer Configuration

open access: yesFrontiers in Energy Research, 2022
Understanding a reliable description of the heat transfer in the molten pool with three-layer configuration is inevitable for the design of severe accident mitigation measures in research reactors, such as IVR-ERVC.
Jian Deng   +9 more
doaj   +1 more source

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

Effect of finned structure on critical heat flux (CHF) in downward-face pool boiling

open access: yesMechanical Engineering Journal, 2020
Critical heat flux (CHF) plays an important role as the upper limit of heat dissipation process during the in-vessel reactor external reactor vessel cooling (IVR-ERVC). IVR-ERVC is regarded as a very effective way to release the decay heat after the core
Kai WANG, Nejdet ERKAN, Koji OKAMOTO
doaj   +1 more source

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

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

open access: yesScience and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 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. In‐Vessel Retention (IVR) is one of the important severe accident management means by External Reactor Vessel Cooling. Reactor cavity would be submerged to cool the molten corium
Dekui Zhan   +5 more
wiley   +1 more source

Home - About - Disclaimer - Privacy