Natural convection test in Phenix reactor and associated CATHARE calculation-Reference-Cited by-同舟云学术

Natural convection test in Phenix reactor and associated CATHARE calculation

Published:2012-12 Issue: Volume:253 Page:23-31
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tenchine D.,Pialla D.,Gauthé P.,Vasile A.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference12 articles.

1. Methodology, status and plans for development and assessment of CATHARE code;Bestion,1999

2. French program for sodium fast reactors;Carbonnier,2007

3. CATHARE 2 V2.5 2: a single version for various applications;Geffraye;Nucl. Eng. Des.,2011

4. Thermohydraulic investigations of decay heat removal systems by natural convection for liquid–metal fast breeder reactors;Hoffmann;Nucl. Technol.,1989

5. Phenix: 35 Years Operation 1974–2009;Martin,2009

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