FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics-Reference-Cited by-同舟云学术

FONESYS: The FOrum & NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

Published:2015-01 Issue: Volume:281 Page:103-113
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Ahn S.H.,Aksan N.,Austregesilo H.,Bestion D.,Chung B.D.,D’Auria F.,Emonot P.,Gandrille J.L.,Hanninen M.,Horvatović I.,Kim K.D.,Kovtonyuk A.,Petruzzi 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

Reference23 articles.

1. Separate effects test matrix for thermal-hydraulic code validation;Aksan,1994

2. User effects on the transient system code calculations;Aksan,1995

3. Comparison between 6 equation and drift flux;Bestion,2011

4. Statements about mesh convergence;Bestion,2011

5. Status and perspective for a multiscale approach to Light Water reactor thermalhydraulic simulation;Bestion;J. Nucl. Eng. Des.,2012

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