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FRAPCON-3.4 [[electronic resource] ] : integral assessment / / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer
| FRAPCON-3.4 [[electronic resource] ] : integral assessment / / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer |
| Autore | Geelhood K. J |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (392 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
LuscherW. G <1979-> (Walter G.)
BeyerC. E |
| Soggetto topico |
Fuel burnup (Nuclear engineering) - Mathematical models - Data processing
Nuclear fuel rods - Mathematical models - Data processing Nuclear fuel claddings - Mathematical models - Data processing Computer-aided engineering |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | FRAPCON-3.4 |
| Record Nr. | UNINA-9910702090403321 |
Geelhood K. J
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
FRAPCON-3.4 [[electronic resource] ] : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup / / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer
| FRAPCON-3.4 [[electronic resource] ] : a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup / / prepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer |
| Autore | Geelhood K. J |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (143 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
LuscherW. G <1979-> (Walter G.)
BeyerC. E |
| Soggetto topico |
Fuel burnup (Nuclear engineering) - Mathematical models - Data processing
Nuclear fuel rods - Mathematical models - Data processing Nuclear fuel claddings - Mathematical models - Data processing Computer-aided engineering |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | FRAPCON-3.4 |
| Record Nr. | UNINA-9910700375603321 |
|
Geelhood K. J
|
||
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
FRAPCON-3.5 / / prepared by K.J. Geelhood and W.G. Luscher
| FRAPCON-3.5 / / prepared by K.J. Geelhood and W.G. Luscher |
| Autore | Geelhood K. J. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 |
| Descrizione fisica | 1 online resource (2 volumes) : color illustrations |
| Soggetto topico |
Nuclear fuel rods - Data processing
Nuclear fuel claddings - Data processing Nuclear fuel rods - Computer simulation Nuclear fuel rods - Computer programs Nuclear power plants - Accidents - Computer simulation Light water reactors - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | v. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup -- v. 2. Integral assessment. |
| Record Nr. | UNINA-9910703833003321 |
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Geelhood K. J.
|
||
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| 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 |
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Geelhood K. J.
|
||
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||