Natural convection heat transfer in corium pools: A review work of experimental studies

L Zhang, Y Zhou, Y Zhang, W Tian, S Qiu… - Progress in Nuclear Energy, 2015 - Elsevier
During a severe accident in nuclear reactors, the core may melt and relocate into the lower
head. The decay power in the accumulated melt pool will threaten the integrity of the reactor …

Live experimental results of melt pool behaviour in the PWR lower head with insulated upper lid and external cooling

X Gaus-Liu, A Miassoedov - International …, 2013 - asmedigitalcollection.asme.org
In-vessel melt retention has drawn renewed concern as an important severe accident
management measure in existing and advanced light water reactors. Despite numerous …

[PDF][PDF] Analysis and Interpretation of the LIVE-L6 Experiment

A Palagin, A Miassoedov, X Gaus-Liu… - 5th European Review …, 2012 - researchgate.net
The thermophysical behaviour of a corium pool in reactor pressure vessel of a pressurised
water reactor is of principal importance for the prediction of core melt down accident …

Influence of boundary conditions, vessel geometry, and simulant materials on the heat transfer of volumetrically heated melt in a light water reactor lower head

X Gaus-Liu, A Miassoedov - Journal of Nuclear …, 2017 - asmedigitalcollection.asme.org
This study investigates heat transfer characters of a volumetrically heated melt pool in LWR
lower plenum. Experimental restrictions on prediction reliability are discussed. These …

Results of the live-L4 experiment on melt behavior in the RPV lower head

A Miassoedov, T Cron, J Foit… - International …, 2010 - asmedigitalcollection.asme.org
The development of a corium pool in the lower head and its behavior is still a critical issue
and is of great importance to assess the severe accident progression consequences to …

LIVE-L4 and LIVE-L5L experiments on melt pool and crust behavior in lower head of reactor pressure vessel

X Gaus-Liu, A Miassoedov, J Foit, T Cron… - Nuclear …, 2013 - Taylor & Francis
Abstract The LIVE-L4 and LIVE-L5L experiments investigated the thermal-hydraulic
behavior of the corium pool in the reactor pressure vessel lower head with the three …

Mechanism-based codes for severe accident analysis

L Zhang - Nuclear Power Plant Design and Analysis Codes, 2021 - Elsevier
Several mechanism-based codes for severe accident (SA) analysis are developed based on
mechanistic models concerning specific phenomena or processes during reactor SAs. The …

CoreSOAR Core Degradation SOAR Update Status May 2017

T Haste, M Barrachin, F Fichot, G Repetto… - 8th European Review …, 2017 - hal.science
In 1991 the OECD Nuclear Energy Agency Committee on Safety of Nuclear Installations
(NEA/CSNI) published the first State-of-the-Art Report (SOAR) on In-Vessel Core …

[PDF][PDF] Coresoar core degradation soar update: summary

T Haste, M Barrachin, F Fichot, G Repetto… - Proc. of the 9th …, 2019 - academia.edu
In 1991 the CSNI published the first State-of-the-Art Report on In-Vessel Core Degradation,
which was updated to 1995 under the EC 3rd Framework programme. These covered …

Research on the non-eutectic phase-change dynamics with heat transfer and component diffusion

L Zhang, Z Ma, Y Zhang, GH Su, W Sun, S Bu… - Applied Thermal …, 2019 - Elsevier
The problem of phase-changing with heat and mass transfer has aroused widespread
interest and imposed new challenges, especially in understanding the non-eutectic phase …