Scaling in nuclear thermal hydraulics: Advances, applications and future perspectives in Spain

Author:

Freixa JordiORCID,Berna César,Escrivá Alberto,Gallardo Sergio,Lorduy-Alós Maria,Martinez-Quiroga Victor,Martin-Gil Kevin,Mendizabal Rafael,Muñoz-Cobo José Luis,Reventós Francesc,Sánchez-Perea Miguel

Publisher

Elsevier BV

Reference43 articles.

1. Csni integral test facility validation matrix for the assessment of thermal-hydraulic codes for lwr locaand transients;Annunziato,1996

2. Analysis of counterpart tests performed in boiling water reactor experimental simulators;Bovalini;Nucl. Technol.,1992

3. Quantifiying reactor safety margins part 1: an overview of the code scaling, applicability, and uncertainty evaluation methodology;Boyack;Nucl. Eng. Des.,1990

4. Post-test analysis of the ROSA/LSTF and PKL counterpart test;Carlos;Nucl. Eng. Des.,2016

5. On the scaling of uncertainties in thermal hydraulic system codes;Casamor;Ann. Nucl. Energy,2020

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