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Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós
| Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 |
| Descrizione fisica | 1 online resource (xvii, 30 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear reactors - Cores |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Core exit temperature response during an Small Break LOss of Coolant Acicident event in the Ascó Nuclear Power Plant |
| Record Nr. | UNINA-9910711961103321 |
Freixa J.
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| Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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
| 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 |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| 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 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703560503321 |
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Freixa J.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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