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FRAPTRAN 1.4 [[electronic resource] ] : a computer code for the transient analysis of oxide fuel rods / / prepared by K.J. Geelhood ... [and others]
| FRAPTRAN 1.4 [[electronic resource] ] : a computer code for the transient analysis of oxide fuel rods / / prepared by K.J. Geelhood ... [and others] |
| Pubbl/distr/stampa | [Washington, DC] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (2 volumes) : color illustrations ; ; 28 cm |
| Altri autori (Persone) | GeelhoodK. J |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear fuel rods - Performance - Analysis |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | FRAPTRAN 1.4 |
| Record Nr. | UNINA-9910700375103321 |
| [Washington, DC] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
FRAPTRAN-1.5 / / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta
| FRAPTRAN-1.5 / / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta |
| Autore | Geelhood K. J. |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 |
| Descrizione fisica | 2 volumes : color illustrations |
| Soggetto topico |
Nuclear fuel rods - Computer simulation
Nuclear fuel rods - Performance - Analysis Nuclear fuel rods - Data processing Nuclear fuel claddings - Data processing Nuclear power plants - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Vol. 1. A computer code for the transient analysis of oxide fuel rods -- vol. 2. Integral assessment. |
| Record Nr. | UNINA-9910704169803321 |
Geelhood K. J.
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| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident [[electronic resource] /] : prepared by Patrick. A.C. Raynaud
| Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident [[electronic resource] /] : prepared by Patrick. A.C. Raynaud |
| Autore | Raynaud Patrick A. C |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] |
| Descrizione fisica | 1 online resource (xvi, 89, A12 pages) : color illustrations |
| Soggetto topico |
Water cooled reactors - Loss of coolant - Analysis
Pressurized water reactors - Loss of coolant - Analysis Nuclear fuel rods - Performance - Analysis Nuclear facilities - Accidents - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Fuel fragmentation, relocation, and dispersal during the loss-of-coolant accident |
| Record Nr. | UNINA-9910701758003321 |
|
Raynaud Patrick A. C
|
||
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
