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 …
COPRA: a large scale experiment on natural convection heat transfer in corium pools with internal heating
L Zhang, Y Zhang, B Zhao, W Ma, Y Zhou… - Progress in Nuclear …, 2016 - Elsevier
During a severe accident in light water reactors, the core may melt and relocate into the
lower plenum of the reactor pressure vessel. The decay heat will threaten the structural and …
lower plenum of the reactor pressure vessel. The decay heat will threaten the structural and …
[HTML][HTML] In-vessel melt retention of pressurized water reactors: historical review and future research needs
W Ma, Y Yuan, BR Sehgal - Engineering, 2016 - Elsevier
ABSTRACT A historical review of in-vessel melt retention (IVR) is given, which is a severe
accident mitigation measure extensively applied in Generation III pressurized water reactors …
accident mitigation measure extensively applied in Generation III pressurized water reactors …
A multiphase MPS method coupling fluid–solid interaction/phase-change models with application to debris remelting in reactor lower plenum
G Duan, A Yamaji, M Sakai - Annals of Nuclear Energy, 2022 - Elsevier
In a postulated severe accident, the in-vessel debris remelting may result in severe local hot
spots, probably threatening the reactor pressure vessel (RPV). The moving particle semi …
spots, probably threatening the reactor pressure vessel (RPV). The moving particle semi …
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 …
volumetrically heated corium melt pools, it is difficult to capture the heat transfer …
Towards the accurate numerical prediction of thermal hydraulic phenomena in corium pools
A Shams - Annals of Nuclear Energy, 2018 - Elsevier
The knowledge of heat transfer in corium pools is one of the important issues for corium
retention, as it defines the safety margin for vessel integrity. In this regard, in the 90's the …
retention, as it defines the safety margin for vessel integrity. In this regard, in the 90's the …
Recent severe accident research synthesis of the major outcomes from the SARNET network
JP Van Dorsselaere, A Auvinen, D Beraha… - … Engineering and Design, 2015 - Elsevier
Abstract The SARNET network (Severe Accident Research NETwork of excellence), co-
funded by the European Commission from 2004 to 2013, has allowed to significantly …
funded by the European Commission from 2004 to 2013, has allowed to significantly …
Creep deformation and damage behavior of reactor pressure vessel under core meltdown scenario
JF Mao, JW Zhu, SY Bao, LJ Luo, ZL Gao - International Journal of …, 2016 - Elsevier
The Fukushima accident shows that In-Vessel Retention (IVR) of molten core debris has not
been appropriately assessed, and a certain pressure (upto 8.0 MPa) still exists inside the …
been appropriately assessed, and a certain pressure (upto 8.0 MPa) still exists inside the …
Numerical study of thermal-hydraulic and structural parameters effects on CHF in subcooled forced convection flow during external reactor vessel cooling
G Liang, Z Zhang, S Bu, H Liu, D Chen - Progress in Nuclear Energy, 2023 - Elsevier
Advanced nuclear reactors employ External Reactor Vessel Cooling (ERVC) as a crucial
measure to safeguard the structural integrity of the Reactor Pressure Vessel's (RPV) lower …
measure to safeguard the structural integrity of the Reactor Pressure Vessel's (RPV) lower …
Investigations on in-vessel melt retention by external cooling for a generic VVER-1000 reactor
P Tusheva, E Altstadt, HG Willschütz, E Fridman… - Annals of Nuclear …, 2015 - Elsevier
External or internal hazards, combined with multiple failures of components and safety
systems or human errors can lead to a reactor core melt. In that case the reactor pressure …
systems or human errors can lead to a reactor core melt. In that case the reactor pressure …