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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
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others]
| Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods
Nuclear reactor accidents - Analysis Pressurized water reactors - Loss of coolant - Analysis Nuclear power plants - Taiwan |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707412703321 |
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Shih Chunkuan
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others]
| Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Nuclear reactor accidents - Analysis
Nuclear reactor accidents - Computer simulation Pressurized water reactors - Loss of coolant - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702555803321 |
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Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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