Investigation on influence of crust formation on VULCANO VE-U7 corium spreading with MPS method
Sign Up to like & getrecommendations! Published in 2017 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.04.002
Abstract: Abstract In a severe accident of a light water reactor, the corium spreading behavior on a containment floor is important as it may threaten the containment vessel integrity. The Moving Particle Semi-implicit (MPS) method is… read more here.
Keywords: crust; corium; mps method; corium spreading ... See more keywords
Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools
Sign Up to like & getrecommendations! Published in 2018 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2017.08.055
Abstract: Abstract Due to the high-Rayleigh-number natural convection and strong turbulence in the volumetrically heated corium melt pools, it is difficult to capture the heat transfer characteristics in detail. The Large Eddy Simulation (LES) methods are… read more here.
Keywords: large eddy; corium; heat transfer; simulation ... See more keywords
Analysis of the configurations and heat transfer of corium pool in RPV lower plenum
Sign Up to like & getrecommendations! Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2018.10.002
Abstract: Abstract The corium containing stainless steel, partially oxidized zirconium cladding and fuel materials in the lower plenum may separate into immiscible liquids at high temperatures that influence the heat flux into vessel during in-vessel melt… read more here.
Keywords: corium; heat; transfer corium; lower plenum ... See more keywords
Concrete ablation analysis for molten corium-concrete interaction mitigation strategy
Sign Up to like & getrecommendations! Published in 2019 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2019.06.057
Abstract: Abstract The molten corium-concrete interaction (MCCI) has been receiving increased attention because it can cause the direct release of core melt into the environment via basemat melt-through (BMT). The MCCI analysis has high uncertainty and… read more here.
Keywords: corium; melt; model; mitigation ... See more keywords
Status of computational fluid dynamics for in-vessel retention: Challenges and achievements
Sign Up to like & getrecommendations! Published in 2020 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2019.107004
Abstract: Abstract During a severe accident in a nuclear reactor, core damage occurs and may lead to the formation of corium, followed by relocation to the vessel lower head. The decay heat released by the corium… read more here.
Keywords: pool; corium; power reactors; status computational ... See more keywords
Experimental study and model development for the high-Rayleigh-number corium pool with heat and mass transfer
Sign Up to like & getrecommendations! Published in 2019 at "International Journal of Heat and Mass Transfer"
DOI: 10.1016/j.ijheatmasstransfer.2019.04.074
Abstract: Abstract The natural convection heat transfer driven by internal decay heat and the diffusive mass transfer at the crust interface are the critical problems in study of thermal behaviors in volumetrically heated reactor corium pools.… read more here.
Keywords: corium; heat; heat mass; transfer ... See more keywords
Investigation of thermo mechanical behaviour in the scaled PHWR stepped calandria vessel during severe accident
Sign Up to like & getrecommendations! Published in 2017 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2017.06.009
Abstract: Abstract In case of Indian Pressurized Heavy Water Reactors (PHWRs), in-calandria retention of corium is essential for mitigating core melt down accident. Benchmark calculations have shown that if corium breaches the calandria vessel and enters… read more here.
Keywords: thermo mechanical; corium; vessel; stepped calandria ... See more keywords
Oxygen diffusion in liquid (over)stoichiometric corium
Sign Up to like & getrecommendations! Published in 2018 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2018.06.027
Abstract: Abstract Within the framework of pressurized water reactor severe accidents, the ICE research program is devoted to studies on a variety of fundamental mechanisms involved in Fuel-Coolant Interaction (FCI). Among them, the oxidation of liquid… read more here.
Keywords: diffusion liquid; corium; diffusion; oxygen diffusion ... See more keywords
Experimental study on natural convection heat transfer in a two-layer corium pool based on COPRA facility
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DOI: 10.1016/j.nucengdes.2019.04.031
Abstract: Abstract During core meltdown accidents, the heat flux distribution along the wall of lower plenum was closely related to the potential of vessel failure. Concerning with the natural convection heat transfer behavior in stratified corium… read more here.
Keywords: pool; corium; heat; layer ... See more keywords
CFD simulation of corium flow through an end fitting of a pressurised heavy water reactor
Sign Up to like & getrecommendations! Published in 2020 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2020.110850
Abstract: Abstract This study investigates the numerical simulation of corium relocation during a hypothetical accident, focussing on the modelling of core melt, its solidification and redistribution. This paper presents results of a high-fidelity computational fluid dynamics… read more here.
Keywords: end fitting; corium; corium flow; geometry ... See more keywords
Measurement of corium surface tension using the maximum bubble pressure
Sign Up to like & getrecommendations! Published in 2021 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2021.111266
Abstract: Abstract The paper proposes a description of the maximum bubble pressure (MBP) technique that has been used to measure the density and the surface tension of high temperature molten materials (up to 2550 °C). The technique… read more here.
Keywords: corium; surface; surface tension; maximum bubble ... See more keywords