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Autore: | Belaïd S. |
Titolo: | Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
Pubblicazione: | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
Descrizione fisica: | 1 online resource (xiii, 29 pages) : color illustrations |
Soggetto topico: | Pressurized water reactors - Testing |
Emergency core cooling systems - Testing | |
Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement | |
Nuclear fuel claddings - Effect of temperature on - Measurement | |
Nuclear power plants - Safety measures - Testing | |
Persona (resp. second.): | FreixaJ |
ZerkakO | |
Note generali: | Title from title screen (viewed Oct. 25, 2013). |
"September 2013." | |
Nota di bibliografia: | Includes bibliographical references (page 29). |
Altri titoli varianti: | Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE |
Titolo autorizzato: | Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE |
Formato: | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione: | Inglese |
Record Nr.: | 9910704812803321 |
Lo trovi qui: | Univ. Federico II |
Opac: | Controlla la disponibilità qui |