B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments-Reference-Cited by-同舟云学术

B4C oxidation modelling in severe accident codes: Applications to PHEBUS and QUENCH experiments

Published:2010-01 Issue:1 Volume:52 Page:37-45
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Repetto G.,De Luze O.,Seiler N.,Trambauer K.,Austregesilo H.,Birchley J.,Ederli S.,Lamy J.S.,Maliverney B.,Drath T.,Hollands T.

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference31 articles.

1. Core loss during a severe accident (COLOSS);Adroguer;Nuclear Engineering and Design,2003

2. Austregesilo, H., C. Bals, K. Trambauer, Post-Test Calculation and Uncertainty Analysis of the Experiment QUENCH-07 with the System Code ATHLET-CD. Proceedings of NURETH-11, Avignon, October 2–6, 2005, France.

3. ATHLET-CD mod 2.1 Cycle A – User's Manual, GRS-P-4;Austregesilo;Gesellschaft für Anlagen- und Reaktorsicherheit,2007

4. Belovsky, L. et al., (1997), Chemical interactions in B4C-filled control rod segments above 1000 °C under transient conditions, ICONE5, paper 2184, May 1997.

5. Chatelard, P. et al, (2006), ‘Assessment of ICARE/CATHARE V1 Severe Accident Code ’ ICONE14 paper 89307, Miami, USA.

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