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 …
head. The decay power in the accumulated melt pool will threaten the integrity of the reactor …
Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers–Results of COPRA experiments
YP Zhang, LT Zhang, YK Zhou, WX Tian, SZ Qiu… - Progress in Nuclear …, 2016 - Elsevier
Large-scale COPRA experiments were performed to investigate the natural convection heat
transfer in melt pools for the in-vessel retention during severe accidents in Chinese large …
transfer in melt pools for the in-vessel retention during severe accidents in Chinese large …
The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head
YP Zhang, LT Zhang, YK Zhou, WX Tian, SZ Qiu… - Annals of Nuclear …, 2016 - Elsevier
Abstract The COPRA (COrium Pool Research Apparatus) facility was designed to
investigate the in-vessel molten corium pool behavior for the in-vessel corium retention …
investigate the in-vessel molten corium pool behavior for the in-vessel corium retention …
COPRA experiments on natural convection heat transfer in a volumetrically heated slice pool with high Rayleigh numbers
L Zhang, Y Zhang, Y Zhou, GH Su, W Tian… - Annals of Nuclear Energy, 2016 - Elsevier
Large scale COPRA experiments were performed to study the natural convection heat
transfer in corium pools inside the reactor pressure vessel lower plenum during severe …
transfer in corium pools inside the reactor pressure vessel lower plenum during severe …
COPRA experiment and numerical research on the behavior of internally-heated melt pool with eutectic salt
S Luo, Y Zhang, Y Zhou, W Tian, GH Su… - Applied Thermal …, 2018 - Elsevier
In-vessel retention (IVR) has been proposed as an effective mitigation strategy during
severe accidents in pressurized water reactors (PWRs). To help understand better the …
severe accidents in pressurized water reactors (PWRs). To help understand better the …
[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 …
water reactor is of principal importance for the prediction of core melt down accident …
Correlations for the bulk temperature and for the Nusselt numbers at the boundary surfaces of a molten steel layer heated from below under the severe accident …
V Loktionov - Nuclear Engineering and Design, 2025 - Elsevier
The paper presents and discusses the correlations for the averaged (bulk) temperature and
for the Nusselt numbers (Nu) on the side and bottom surfaces of a layer of molten steel …
for the Nusselt numbers (Nu) on the side and bottom surfaces of a layer of molten steel …
In-and ex-vessel coupled analysis for in-vessel retention
Y Luo, X Liu, X Cheng - Progress in Nuclear Energy, 2018 - Elsevier
In-vessel retention (IVR) in the manner of external reactor vessel cooling (ERVC) is an
important severe accident mitigation strategy, which has been applied to some advanced …
important severe accident mitigation strategy, which has been applied to some advanced …
Safety research of IVR-ERVC for advanced water cooled reactor
X Liu, Y Luo, C Zhen, R Guo, X Cheng - Energy, 2018 - Elsevier
After Fukushima accident, more and more attention has been paid on severe accident
analysis. As an important severe accident mitigation strategy applied to advanced light water …
analysis. As an important severe accident mitigation strategy applied to advanced light water …
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 …
behavior of the corium pool in the reactor pressure vessel lower head with the three …