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Analysis of pin-by-pin effects for LWR rod ejection accident / / prepared by A. Avvakumov, V. Malofeev, V. Sidorov
| Analysis of pin-by-pin effects for LWR rod ejection accident / / prepared by A. Avvakumov, V. Malofeev, V. Sidorov |
| Autore | Avvakumov A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2000 |
| Descrizione fisica | 1 online resource (xi, 77 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear fuel rods - Accidents - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of pin by pin effects for LWR rod ejection accident |
| Record Nr. | UNINA-9910707211503321 |
Avvakumov A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà
| Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà |
| Autore | Muñoz-Cobo J. L. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (37 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis with TRAC/RELAP Advanced Computational Engine code of PKL-III test F 1.2 |
| Record Nr. | UNINA-9910704414903321 |
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Muñoz-Cobo J. L.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / / Prepared by: Sebastian Gurgacz [and five others]
| EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / / Prepared by: Sebastian Gurgacz [and five others] |
| Autore | Gurgacz Sebastian |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 |
| Descrizione fisica | 1 online resource (57 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Light water reactors - Accidents - Computer simulation Nuclear power plants - Design and construction - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | European Pressurized Reactor medium break Loss Of Coolant Accident benchmarking exercise using Reactor Excursion and Leak Analysis Program5 and Code for Analysis of Thermal Hydraulics during an Accident of Reactor and safety Evaluation |
| Record Nr. | UNINA-9910704262503321 |
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Gurgacz Sebastian
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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 | ||
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Material property correlations : comparisons between FRAPCON-3.5, FRAPTRAN-1.5, and MATRO / / prepared by W.G. Luscher and K.J. Geelhood
| Material property correlations : comparisons between FRAPCON-3.5, FRAPTRAN-1.5, and MATRO / / prepared by W.G. Luscher and K.J. Geelhood |
| Autore | Luscher W. G (Walter G.), <1979-> |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 |
| Descrizione fisica | 1 online resource (153 unnumbered pages) : color illustrations |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
Light water reactors - Accidents - Computer simulation Nuclear reactors - Materials Nuclear fuel rods - Data processing Nuclear fuel claddings - Data processing Nuclear fuel rods - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Material property correlations |
| Record Nr. | UNINA-9910702746903321 |
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Luscher W. G (Walter G.), <1979->
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Material property correlations [[electronic resource] ] : comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO / / prepared by W.G. Luscher and K.J. Geelhood
| Material property correlations [[electronic resource] ] : comparisons between FRAPCON-3.4, FRAPTRAN 1.4, and MATPRO / / prepared by W.G. Luscher and K.J. Geelhood |
| Autore | Luscher W. G (Walter G.), <1979-> |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (57 unnumbered pages) : illustrations |
| Altri autori (Persone) | GeelhoodK. J |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Material Property Correlations |
| Record Nr. | UNINA-9910703134103321 |
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Luscher W. G (Walter G.), <1979->
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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 | ||
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Regulatory guide 1.195 [[electronic resource] ] : methods and assumptions for evaluating radiological consequences of design basis accidents at light-water nuclear power reactors
| Regulatory guide 1.195 [[electronic resource] ] : methods and assumptions for evaluating radiological consequences of design basis accidents at light-water nuclear power reactors |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2003] |
| Descrizione fisica | 58 unnumbered pages : digital, PDF file |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Regulatory guide 1.195 |
| Record Nr. | UNINA-9910697808303321 |
| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2003] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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