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Autore: | Freixa J. |
Titolo: | Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
Pubblicazione: | Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 |
Descrizione fisica: | 1 online resource (73 unnumbered pages) : color illustrations |
Soggetto topico: | Nuclear power plants - Accidents - Computer simulation |
Nuclear power plants - Computer programs - Testing | |
Pressurized water reactors - Loss of coolant - Computer simulation | |
Nuclear reactor accidents - Computer simulation | |
Note generali: | Title from title screen (viewed April 8, 2015). |
"Manuscript completed: April 2011 ; Date published: October 2014." | |
Nota di bibliografia: | Includes bibliographical references (page 7-1). |
Titolo autorizzato: | Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 |
Formato: | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione: | Inglese |
Record Nr.: | 9910703560503321 |
Lo trovi qui: | Univ. Federico II |
Opac: | Controlla la disponibilità qui |