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Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, version 3690, code / / F. Odar [and seven others]
| Assessment of modernization and integration of BWR components and spatial kinetics in the TRAC-M, version 3690, code / / F. Odar [and seven others] |
| Autore | Odar Fuat |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2001 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Boiling water reactors - Computer programs - Evaluation
Nuclear power plants - Accidents - Computer programs - Evaluation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708667503321 |
Odar Fuat
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data / / prepared by F. Odar
| Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data / / prepared by F. Odar |
| Autore | Odar Fuat |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2001 |
| Descrizione fisica | 1 online resource (xi, 82 pages) : illustrations |
| Soggetto topico |
Pressurized water reactors - Thermodynamics - Computer programs
Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment of the TRAC M codes using Flecht-Seaset reflood and steam cooling data |
| Record Nr. | UNINA-9910708659503321 |
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Odar Fuat
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Software quality assurance procedures for NRC thermal hydraulic codes / / prepared by F. Odar
| Software quality assurance procedures for NRC thermal hydraulic codes / / prepared by F. Odar |
| Autore | Odar Fuat |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 2000 |
| Descrizione fisica | 1 online resource (ix, 73 pages) : illustrations |
| Soggetto topico |
Nuclear power plants - Thermodynamics - Computer programs
Nuclear reactors - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Software quality assurance procedures for Nuclear Regulatory Commission thermal hydraulic codes |
| Record Nr. | UNINA-9910708658903321 |
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Odar Fuat
|
||
| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||