Results of an experiment in a Zion-like geometry to investigate the effect of water on the containment basement floor on direct containment heating (DCH) in the Surtsey Test Facility: The IET-4 test (original) (raw)

Test results on direct containment heating by high-pressure melt ejection into the Surtsey vessel: The TDS test series

1994

Melt Dispersion and Direct Containment Heating (DCH) Experiments in the DISCO-H Test Facility

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Nuclear Engineering and Design, 1995

United States Nuclear Regulatory Commission Research Program on molten core debris interactions in the reactor cavity

John Brockmann

Nuclear Engineering and Design, 1989

Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant

1997

Direct Containment Heating Investigations for European Pressurized Water Reactors

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Jarto Niemi

Corium Dispersion and Direct Containment Heating Experiments at Low System Pressure

Results from the DCH-1 (Direct Containment Heating) experiment. [Pressurized melt ejection and direct containment heating]

1987

Experimental simulation of corium dispersion phenomena in direct containment heating

Shripad Revankar

Nuclear Engineering and Design, 1996

Experiments to investigate the effect of flight path on direct containment heating

Nuclear Technology - NUCL TECHNOL, 1992

Investigations of Direct Containment Heating (DCH) in European Reactors: Database of Integral Tests and Progress in Modeling

High pressure simulation experiment on corium dispersion in direct containment heating

Shripad Revankar

Nuclear Engineering and Design, 1996

The 15 th International Topical Meeting on Nuclear Reactor Thermal -Hydraulics, NURETH-15 PRELIMINARY ASSESSMENT OF THE THERMAL INTERACTION AMONG CORIUM AND IN-VESSEL CORE CATCHER IN A LARGE SODIUM FAST REACTOR

Flavio Parozzi

Insights into the behavior of nuclear power plant containments during severe accidents

J. Rashid

1993

Heat and Mass Transfer of High Performance Concrete for Reactor Containment Under Severe Accident Conditions

Mohammad Shekarchi

Fire Technology

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Antonio Lloret

Géotechnique, 2009

Experimental study on the heat transfer characteristics of a nuclear reactor containment wall cooled by gravitationally falling water

ari pasek

2012

Pressure and temperature analyses using GOTHIC for Mark I containment of the Chinshan Nuclear Power Plant

Yng-ruey yuann

Nuclear Engineering and Design, 2011

LIVE Experiments on Melt Behavior in the Reactor Pressure Vessel Lower Head

Major Major

Heat Transfer Engineering, 2013

Modeling of corium melt cooling during severe accidents at the nuclear power plants

Ivan Kazachkov

Simulation of containment thermal-hydraulics in the Marviken Blowdown 16 experiment with ASTEC and CONTAIN codes

Ivo Kljenak

Nuclear Engineering and Design, 2011

Integrated assessment of thermal hydraulic processes in W7-X fusion experimental facility

Algirdas Kaliatka

Nuclear Engineering and Design, 2016

Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA

Salih Guentay

Nuclear Engineering and Design, 2001

High-Temperature Characterization of Melted Nuclear Core Materials: Investigating Corium Properties Through the Case Studies of In-Vessel and Ex-Vessel Retention

Christophe Journeau

Frontiers in Energy Research

Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions

Herranz Puebla Luis Enrique

Nuclear Engineering and Design, 1998

Scaling and design analyses of a scaled-down, high-temperature test facility for experimental investigation of the initial stages of a VHTR air-ingress accident

Xiaodong Sun

Nuclear Engineering and Design, 2015

Feasibility of constructing a full-scale radioactive high-level waste disposal cell and characterization of its thermo-hydro-mechanical behavior

Antonio Gens

International Journal of Rock Mechanics and Mining Sciences, 2021

The probability of containment failure by direct containment heating in Zion

Nuclear Engineering and Design, 1996

Assessment of the possibility of core melt containment in a BBER-640 vessel

I. Likhachev

Atomic Energy, 1996

Evaluation of heat-flux distribution at the inner and outer reactor vessel walls under the in-vessel retention through external reactor vessel cooling condition

Sang Ho An

Nuclear Engineering and Technology, 2015

Behaviour of a prestressed reactor pressure vessel for HTR under extremely high core temperature loading

Dr. Klaus Schimmelpfennig

International Journal of Pressure Vessels and Piping, 1983

Transactions of the Korean Nuclear Society Virtual Autumn Meeting December 17-18 Numerical Analysis of Algebraic Heat Flux Model in a Rectangular Cavity

Ralph Carlo Evidente

2020