Modelling guidelines for core exit temperature simulations with system codes-Reference-Cited by-同舟云学术

Modelling guidelines for core exit temperature simulations with system codes

Published:2015-05 Issue: Volume:286 Page:116-129
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Freixa J.^ORCID,Martínez-Quiroga V.,Zerkak O.,Reventós F.

Funder

Spanish Safety Council (CSN)

Swiss Federal Nuclear Safety Inspectorate ENSI

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

Reference21 articles.

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2. Separate effects test matrix for thermal-hydraulic code validation;Aksan,1993

3. Post-test thermal-hydraulic analysis of two intermediate {LOCA} tests at the {ROSA} facility including uncertainty evaluation;Freixa;Nucl. Eng. Des.,2013

4. Analysis of an RPV upper head SBLOCA at the ROSA facility using TRACE;Freixa;Nucl. Eng. Des.,2010

5. Remarks on consistent development of plant nodalizations: an example of application to the ROSA integral test facility;Freixa;Sci. Technol. Nucl. Install.,2012

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