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] | ||
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Lo trovi qui: Univ. Federico II | ||
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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 | ||
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Lo trovi qui: Univ. Federico II | ||
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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
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Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] | ||
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Lo trovi qui: Univ. Federico II | ||
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