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 …

Large eddy simulation on turbulent heat transfer in reactor vessel lower head corium pools

L Zhang, S Luo, Y Zhang, W Tian, GH Su, S Qiu - Annals of Nuclear Energy, 2018 - Elsevier
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 …

Study on structural failure of RPV with geometric discontinuity under severe accident

JF Mao, JW Zhu, SY Bao, LJ Luo, ZL Gao - Nuclear Engineering and …, 2016 - Elsevier
A severe accident management strategy known as 'in-vessel retention (IVR)'is widely
adopted in most of advanced nuclear power plants. The IVR mitigation is assumed to be …

Review of experimental study on melt pool natural convection behavior

H Wei, YT Chen, J Cheng - Annals of Nuclear Energy, 2018 - Elsevier
In a hypothetical severe accident that happens in a light water reactor (LWR), the melt pool
could be formed in the lower plenum of reactor pressure vessel (RPV). Remaining these …

LIVE experiments on melt behavior in the reactor pressure vessel lower head

A Miassoedov, T Cron, X Gaus-Liu… - Heat transfer …, 2013 - Taylor & Francis
The main objective of the LIVE program at Karlsruhe Institute of Technology is to study the
core melt phenomena both experimentally in large-scale three-dimensional (3D) geometry …

Study on structural integrity of reactor pressure vessel with various ablation under core meltdown accident

A Liao, J Yang, T Jin, P Liu, D Wang, J Mao - Nuclear Engineering and …, 2022 - Elsevier
In-vessel retention is an important measure to alleviate the core meltdown accident in the
third generation nuclear power plant. External Reactor Vessel Cooling (ERVC) is the key to …

Investigation on the RPV structural behaviors caused by various cooling water levels under severe accident

J Mao, L Hu, S Bao, L Luo, Z Gao - Engineering Failure Analysis, 2017 - Elsevier
In the severe accident (SA) event of core meltdown, the 'In-vessel retention (IVR)'mitigation
has been certified as an effective strategy for accident management in most advanced …

[图书][B] Test and simulation results of LIVE-L4+ LIVE-L5L

X Gaus-Liu, A Mjasoedov, T Cron, JJ Foit, B Fluhrer… - 2011 - books.google.com
The sequence of a postulated core melt down accident in the reactor pressure vessel (RPV)
of a pressurised water reactor (PWR) involves a large number of complex physical and …

Numerical investigation of convection heat transfer characteristics in sloshing corium pools

J Deng, L Song, L Pan, B Liu, J Lu, L Xu - Nuclear Engineering and Design, 2022 - Elsevier
The convection flow and heat transfer actuated by internal decay heat and the sloshing of
vessels are the primary problems in the study of thermal behaviors in volumetrically heated …

Modified Relationship for Nusselt Numbers on the Side Surface of a Flat Metal Layer of Melt Heated from Below

VD Loktionov - Thermal Engineering, 2023 - Springer
An analysis was made of the developed modified Nusselt number ratio Nu for estimating
thermal loads on the surfaces of a flat horizontal layer of metal melt (liquid-metal coolants …