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 …

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 …

Transient refractory material dissolution by a volumetrically-heated melt

JM Seiler, G Ratel, H Combeau, X Gaus-Liu… - … Engineering and Design, 2014 - Elsevier
The present work addresses the question of corium–ceramic interaction in a core catcher
during a core-melt accident in a nuclear power plant. It provides an original insight into …

Calculation of corium-refractory material interaction with the TIM model

JM Seiler, N Seiler - Nuclear Engineering and Design, 2023 - Elsevier
Core-catchers made of ceramic materials have been considered to stabilize corium pool in
case of severe accidents due to the high melting temperature of ceramics. The design of …

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 …

[PDF][PDF] 熔融池相变传热特性的大涡模拟数值研究

席治国, 张卢腾, 胡钰文, 宫厚军, 马在勇, 孙皖… - 核动力 …, 2022 - hdlgc.xml-journal.net
研究反应堆熔融池内部的流动与传热特性对保证熔融物堆内滞留具有重要意义.
本文基于开源软件OpenFOAM 平台, 结合大涡模拟湍流方法和熔融池相变过程建立熔融池传热 …

Performance analysis of natural convection in presence of internal heating, strong turbulence and phase change

L Zhang, J Deng, W Sun, Z Ma, GH Su, L Pan - Applied Thermal …, 2020 - Elsevier
Experimental study and numerical simulation work were carried out to investigate the natural
convection performance in presence of internal heating, strong turbulence and phase …

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 …

Margin evaluation of in-vessel melt retention for small IPWR

N Jiang, T Cong, M Peng - Progress in Nuclear Energy, 2019 - Elsevier
In this paper, the safety margin of IVR (in-vessel melt retention) for small IPWR IP200
(integrated pressurized water reactor) is evaluated by numerical simulation. The thermal …