A review on analysis of LWR severe accident

YP Zhang, SP Niu, LT Zhang… - Journal of …, 2015 - asmedigitalcollection.asme.org
A severe accident (SA) is defined as an incident involving melting of the nuclear reactor core
and the release of fission products (FP) from the fuel and their associated risks. In the SA …

Premixing and steam explosion phenomena in the tests with stratified melt-coolant configuration and binary oxidic melt simulant materials

P Kudinov, D Grishchenko, A Konovalenko… - … Engineering and Design, 2017 - Elsevier
Steam explosion phenomena in stratified melt-coolant configuration are considered in this
paper. Liquid corium layer covered by water on top can be formed in severe accident …

An experimental study on pressure drop and dryout heat flux of two-phase flow in packed beds of multi-sized and irregular particles

L Li, W Ma, S Thakre - Nuclear engineering and design, 2012 - Elsevier
This paper is concerned with debris bed coolability in a postulated severe accident of light
water reactors, where the debris particles are irregular and multi-sized. To obtain and verify …

Experimental results on pouring and underwater liquid melt spreading and energetic melt-coolant interaction

A Konovalenko, A Karbojian… - The 9th International …, 2012 - diva-portal.org
In a hypothetical light water reactor (LWR) core-melt accident with corium release from the
reactor vessel, the ultimate containment integrity is contingent on coolability of the decay …

Insight into steam explosion in stratified melt-coolant configuration

D Grishchenko, A Konovalenko, A Karbojian… - … 15, 12 to 17 May, 2013 …, 2013 - diva-portal.org
Release of core melt from failed reactor vessel into a pool of water is adopted in several
existing designs of light water reactors (LWRs) as an element of severe accident mitigation …

Development and validation of conservative-mechanistic and best estimate approaches to quantifying mass fractions of agglomerated debris

P Kudinov, M Davydov - Nuclear Engineering and Design, 2013 - Elsevier
Ex-vessel termination of accident progression in Swedish type Boiling Water Reactors
(BWRs) is contingent upon efficacy of melt fragmentation, quenching, solidification and …

Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a Nordic type BWR

D Grishchenko, S Galushin, P Kudinov - Nuclear Engineering and Design, 2019 - Elsevier
Sever accident mitigation strategy adopted in Nordic Boiling Water Reactors (BWRs)
employs a deep water pool below the reactor vessel to fragment and quench core melt and …

[PDF][PDF] Investigation of steam explosion in stratified melt-coolant configuration

P Kudinov, D Grishchenko… - … Topical Meting on …, 2014 - researchgate.net
We consider steam explosion in stratified melt–coolant configuration. Such configuration,
with a liquid corium layer covered by water on top, can be formed in severe accident …

Coolability of heat-releasing debris bed. Part 1: Sensitivity analysis and model calibration

SE Yakush, P Kudinov, NT Lubchenko - Annals of Nuclear Energy, 2013 - Elsevier
Coolability of heat-releasing debris bed is an important issue in the severe accident analysis
and management. Traditionally, theoretical studies of top or bottom-fed debris bed …

[PDF][PDF] Effect of corium non-homogeneity on nordic BWR vessel failure mode and timing

A Goronovski, W Villanueva, P Kudinov… - Proceedings of …, 2015 - researchgate.net
Corium melt fragmentation and cooling in a deep pool of water under reactor pressure
vessel are employed as severe accident mitigation strategy in a Nordic-type BWR. Core …