Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident-Reference-Cited by-同舟云学术

Modelling nuclear fuel behaviour with TAF-ID: Calculations on the VERDON-1 experiment, representative of a nuclear severe accident

Published:2019-08 Issue: Volume:522 Page:294-310
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Geiger E.,Guéneau C.,Pontillon Y.,Corcoran E.C.

Funder

CANDU Owners Group

Natural Sciences and Engineering Research Council of Canada

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference26 articles.

1. FUELBASE, TAF-ID Databases and OC Software: Advanced Computational Tools to Perform Thermodynamic Calculations on Nuclear Fuel Materials;Guéneau,2015

2. CALPHAD (Calculation of Phase Diagrams): A Comprehensive Guide;Saunders,1998

3. International Source Term Program - VERDON-1 Test: Fission Product Release from a High Burn-Up UO2 Fuel in Severe Accident Conditions: Final Report;Pontillon,2012

4. Fission products and nuclear fuel behaviour under severe accident conditions part 1: main lessons learnt from the first VERDON test;Pontillon;J. Nucl. Mater.,2017

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