TAF-ID: An international thermodynamic database for nuclear fuels applications
Abstract The Thermodynamics of Advanced Fuels–International Database (TAF-ID) was
developed using the Calphad method to provide a computational tool to perform …
developed using the Calphad method to provide a computational tool to perform …
The effective convectivity model for simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part I: Physical processes, modeling and …
CT Tran, TN Dinh - Progress in Nuclear Energy, 2009 - Elsevier
This paper, and its companion paper [Tran CT, Dinh, TN The effective convectivity model for
simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part …
simulation of melt pool heat transfer in a light water reactor pressure vessel lower head. Part …
Corium experimental thermodynamics: a review and some perspectives
M Barrachin - Thermo, 2021 - mdpi.com
More than 30 years ago a specialist meeting was held at Joint Research Center Ispra (Italy)
from 15 to 17 January 1990 to review the current understanding of chemistry during severe …
from 15 to 17 January 1990 to review the current understanding of chemistry during severe …
Modelling issues related to molten pool behaviour in case of In-Vessel Retention strategy
L Carénini, F Fichot, N Seignour - Annals of Nuclear Energy, 2018 - Elsevier
Abstract The In-Vessel Retention (IVR) strategy for Light Water Reactors (LWR) intends to
stabilize and retain the core melt in the reactor pressure vessel. This type of Severe Accident …
stabilize and retain the core melt in the reactor pressure vessel. This type of Severe Accident …
Transient stratification modelling of a corium pool in a LWR vessel lower head
R Le Tellier, L Saas, S Bajard - Nuclear Engineering and Design, 2015 - Elsevier
In the context of light water reactor severe accidents analysis, this paper is focused on one
key parameter of in-vessel corium phenomenology: the immiscible phases stratification and …
key parameter of in-vessel corium phenomenology: the immiscible phases stratification and …
Contribution to the thermodynamic description of the corium–The U-Zr-O system
A Quaini, C Guéneau, S Gossé, N Dupin… - Journal of Nuclear …, 2018 - Elsevier
In order to understand the stratification process that may occur in the late phase of the fuel
degradation during a severe accident in a PWR, the thermodynamic knowledge of the U-Zr …
degradation during a severe accident in a PWR, the thermodynamic knowledge of the U-Zr …
Severe accident management concept of the VVER-1000 and the justification of corium retention in a crucible-type core catcher
VB Khabensky, VS Granovsky, SV Bechta… - Nuclear Engineering …, 2009 - koreascience.kr
First ex-vessel core catcher has been applied to the practical design of NPPs with VVER-
1000 reactors built in China (Tyanvan) and India (Kudankulam) for severe accident …
1000 reactors built in China (Tyanvan) and India (Kudankulam) for severe accident …
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 …
Comparison of the observed Fukushima Dai-Ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test
A Pshenichnikov, Y Nagae, M Kurata - Journal of Nuclear Science …, 2021 - Taylor & Francis
ABSTRACT In February 2019, TEPCO and TOSHIBA designed a robot that can handle the
debris, performed a trial investigation of primary containment vessel (PCV) of the Fukushima …
debris, performed a trial investigation of primary containment vessel (PCV) of the Fukushima …
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 …