International benchmark on the natural convection test in Phenix reactor-Reference-Cited by-同舟云学术

International benchmark on the natural convection test in Phenix reactor

Published:2013-05 Issue: Volume:258 Page:189-198
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tenchine D.,Pialla D.,Fanning T.H.,Thomas J.W.,Chellapandi P.,Shvetsov Y.,Maas L.,Jeong H.-Y.,Mikityuk K.,Chenu A.,Mochizuki H.,Monti S.

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. Analysis of selected Phenix EOL tests with the FAST code system – Part II: Unprotected phase of the Natural Convection Test;Chenu;Ann. Nucl. Energy,2012

2. 3-D thermal hydraulic analysis of transient heat removal from fast reactor core using immersion coolers;Chvetsov,1998

3. The SAS4A/SASSYS-1 Safety Analysis Code System. ANL/NE-12/4, Nuclear Engineering Division,2012

4. Ha, K.S., et al., 2007. Development of MARS-LMR and steady state calculation for KALIMER-600. Report KAERI/TR-3418/2007, Korea Atomic Energy Research Institute, Korea.

5. Martin, L., et al., 2009. The Phenix reactor: assessment of 35 years operation. Revue Générale du Nucléaire 1.

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