Results 201 to 210 of about 401 (227)

Numerical analysis of simulant effect on natural convection characteristics in corium pools

Applied Thermal Engineering, 2019
Abstract In-vessel retention (IVR) is considered as an effective mitigation strategy in realms of nuclear safety. Extensive experimental investigations have been done on the natural convection characteristics of corium pools according to the IVR concept, using various simulant materials.
Simin Luo, Yapei Zhang, Dalin Zhang, G.H. Su, Suizheng Qiu   +4 more
openaire   +1 more source

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

Progress in Nuclear Energy, 2015
Abstract 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 vessel if there is no effective cooling mechanism. Natural convection plays an important role in determining the heat flux distribution from the debris pool,
Luteng Zhang, Yukun Zhou, Yapei Zhang, Wenxi Tian, Suizheng Qiu, Guanghui Su   +5 more
openaire   +1 more source

Research on IVR-Relevant Phenomena of Material Thermodynamic Interaction and Corium Pool Configuration

Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, 2017
In-Vessel Retention (IVR), which arrests relocated molten core materials in the vessel during severe accident, has been singled out as an appealing accident management approach to many reactors. The heat transfer imposed by in-vessel corium is a vital part for IVR success considering the difficulty of significantly altering ex-vessel CHF.
Peiwen Gu, Guobao Shi, Kemei Cao, Jiayun Wang   +3 more
openaire   +1 more source

Towards the accurate numerical prediction of thermal hydraulic phenomena in corium pools

Annals of Nuclear Energy, 2018
Abstract 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 BALI experimental program was performed at the CEA, France.
openaire   +1 more source

Experimental study of transient phenomena in the three-liquid oxidic-metallic corium pool

Nuclear Engineering and Design, 2018
Non-steady physicochemical phenomena in the three-liquid molten pool of prototypic corium are studied in the context of in-vessel melt retention problem. Experiments are made on the Rasplav-3 test facility within the CORDEB program. Structure of the initial molten pool consists of the surface light melt of molten steel, the intermediate layer of oxidic
V.I. Almjashev, V.S. Granovsky, V.B. Khabensky, S.Yu. Kotova, E.V. Krushinov, A.A. Sulatsky, S.A. Vitol, V.V. Gusarov, F. Fichot, B. Michel, P. Piluso, R. Le Tellier, M. Fischer, C. Le Guennic, N. Bakouta   +14 more
openaire   +1 more source

Wash out kinetics of Na from the transport pool to the epithelial and corium side of the frog skin

Pfl�gers Archiv European Journal of Physiology, 1972
The wash out kinetics of Na-24 out of the transport pool of the frog skin were followed simultaneously to the epithelial and corium side in control experiments and after inhibition of the Na transport with ouabain. A perfusion system was used which allowed changes of the perfusion chambers within 5 sec between labelling and tracer wash out.
A, Dörge, W, Nagel
openaire   +2 more sources

High temperature experimental contribution to the thermodynamic modeling of corium pools

2016
During a severe accident in a Pressurized or Boiling Water nuclear reactor, extreme temperatures may be reached (T>2500 K). Under these conditions, the oxide fuel (UO2) may react with the Zircaloy cladding and with the steel vessel, forming a mixture of solid-liquid phases called in-vessel corium.
Gossé, S., Quaini, A., Guéneau, C., Alpettaz, T., Lizon a Lugrin, E., Dupin, N., Poissonnet, S., Bonnaillie, P.   +7 more
openaire   +1 more source

Effect of temperature gradient on chemical element partitioning in corium pool during in-vessel retention

Nuclear Engineering and Design, 2018
The paper presents some results of the ISTC (International Science and Technology Center)-financed project ‘Investigation of Corium Melt Interaction with NPP Reactor Vessel Steel’ (METCOR).
Khabensky, V. B., Granovsky, V. S., Almjashev, V. I., Vitol, S. A., Krushinov, E. V., Kotova, S. Ju., Sulatsky, A. A., Gusarov, V. V., Bechta, S. V., Barrachin, M., Bottomley, D., Fischer, M., Hellmann, S., Piluso, P., Miassoedov, A., Tromm, W.   +15 more
openaire   +2 more sources

Corium Pool Behaviour in the Core Catcher of a Sodium-Cooled Fast Reactor

SSRN Electronic Journal, 2022
R. Clavier, M. Johnson, B. Bigot
openaire   +1 more source

Validation and application of numerical modeling for in-vessel melt retention in corium pools

International Journal of Heat and Mass Transfer, 2022
Avadhesh Kumar Sharma, Marco Pellegrini, Koji Okamoto, Masahiro Furuya, Shinya Mizokami   +4 more
openaire   +1 more source