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CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident / / prepared by C.F. Boyd, K. Hardesty
| CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident / / prepared by C.F. Boyd, K. Hardesty |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2003 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Pressurized water reactors - Accidents
Nuclear reactor accidents Nuclear power plants - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Computational fluid dynamics analysis of one-seventh scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident |
| Record Nr. | UNINA-9910705696503321 |
Boyd Christopher Fred
|
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2003 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident / / C.F. Boyd, D.M. Helton, K. Hardesty
| CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident / / C.F. Boyd, D.M. Helton, K. Hardesty |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2004 |
| Descrizione fisica | 1 online resource (xi, 72 pages) : illustrations |
| Soggetto topico |
Pressurized water reactors - Accidents
Nuclear reactor accidents Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
CFD analysis of full scale steam generator inlet plenum mixing during a PWR severe accident
Computational fluid dynamics analysis of full-scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident |
| Record Nr. | UNINA-9910705696803321 |
|
Boyd Christopher Fred
|
||
| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2004 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Computational fluid dynamics analysis of natural circulation flows in a pressurized-water reactor loop under severe accident conditions [[electronic resource] /] / prepared by C.F. Boyd and K.W. Armstrong
| Computational fluid dynamics analysis of natural circulation flows in a pressurized-water reactor loop under severe accident conditions [[electronic resource] /] / prepared by C.F. Boyd and K.W. Armstrong |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (78 pages) : illustrations |
| Altri autori (Persone) | ArmstrongK. W |
| Soggetto topico |
Computational fluid dynamics - Accidents
Steam generating heavy water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697025703321 |
|
Boyd Christopher Fred
|
||
| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||