Assessment of TRACE 5.0 against ROSA-2 test 3 countertest to PKL / / prepared by S. Gallardo [and three others]
| Assessment of TRACE 5.0 against ROSA-2 test 3 countertest to PKL / / prepared by S. Gallardo [and three others] |
| Autore | Gallardo S. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 |
| Descrizione fisica | 1 online resource (xvii, 37 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Computer programs Nuclear power plants - Accidents Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910712080003321 |
Gallardo S.
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 | ||
| Lo trovi qui: Univ. Federico II | ||
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CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident / / prepared by C.F. Boyd, K. Hardesty
| CFD analysis of 1/7th scale steam generator inlet plenum mixing during a PWR severe accident / / prepared by C.F. Boyd, K. Hardesty |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2003 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Pressurized water reactors - Accidents
Nuclear reactor accidents Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Computational fluid dynamics analysis of one-seventh scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident |
| Record Nr. | UNINA-9910705696503321 |
Boyd Christopher Fred
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2003 | ||
| Lo trovi qui: Univ. Federico II | ||
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CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident / / C.F. Boyd, D.M. Helton, K. Hardesty
| CFD analysis of full-scale steam generator inlet plenum mixing during a PWR severe accident / / C.F. Boyd, D.M. Helton, K. Hardesty |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2004 |
| Descrizione fisica | 1 online resource (xi, 72 pages) : illustrations |
| Soggetto topico |
Pressurized water reactors - Accidents
Nuclear reactor accidents Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
CFD analysis of full scale steam generator inlet plenum mixing during a PWR severe accident
Computational fluid dynamics analysis of full-scale steam generator inlet plenum mixing during a pressurized-water reactor severe accident |
| Record Nr. | UNINA-9910705696803321 |
Boyd Christopher Fred
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2004 | ||
| Lo trovi qui: Univ. Federico II | ||
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Fuel damage during cleaning at a foreign pressurized water reactor [[electronic resource]]
| Fuel damage during cleaning at a foreign pressurized water reactor [[electronic resource]] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [2004] |
| Descrizione fisica | 1 online resource (3, 1 page) |
| Collana | NRC information notice |
| Soggetto topico |
Pressurized water reactors - Accidents
Nuclear fuels - Cleaning |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699678303321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [2004] | ||
| Lo trovi qui: Univ. Federico II | ||
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Overpressurization of containment of a PWR plant after a main steam line break
| Overpressurization of containment of a PWR plant after a main steam line break |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1979 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Pressurized water reactors - Accidents - United States
Nuclear reactors - Containment Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Overpressurization of containment of a pressurized water reactor plant after a main steam line break |
| Record Nr. | UNINA-9910711785603321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1979 | ||
| Lo trovi qui: Univ. Federico II | ||
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Recent hammer events
| Recent hammer events |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1985 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Water hammer
Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715034503321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1985 | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5/MOD2 analysis of LOFT experiment L9-4 / / prepared by M.B. Keevill
| RELAP5/MOD2 analysis of LOFT experiment L9-4 / / prepared by M.B. Keevill |
| Autore | Keevill M. B. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 |
| Descrizione fisica | 1 online resource (33 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents
Pressurized water reactors - Loss of coolant LOFT (Nuclear reactor safety test facility) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707780203321 |
Keevill M. B.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 | ||
| Lo trovi qui: Univ. Federico II | ||
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SCDAP/RELAP5 thermal-hydraulic evaluations of the potential for containment bypass during extended station blackout severe accident sequences in a Westinghouse four-loop PWR [[electronic resource] /] / prepared by C.D. Fletcher ... [and others]
| SCDAP/RELAP5 thermal-hydraulic evaluations of the potential for containment bypass during extended station blackout severe accident sequences in a Westinghouse four-loop PWR [[electronic resource] /] / prepared by C.D. Fletcher ... [and others] |
| Pubbl/distr/stampa | Wash9ngton, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (246 unnumbered pages) : illustrations |
| Altri autori (Persone) | FletcherC. Don |
| Soggetto topico |
Nuclear power plants
Electric power failures Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699740903321 |
| Wash9ngton, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Lo trovi qui: Univ. Federico II | ||
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Simulation of ROSA-2 test-2 experiment : application to nuclear power plant / / prepared by S. Gallardo [and three others]
| Simulation of ROSA-2 test-2 experiment : application to nuclear power plant / / prepared by S. Gallardo [and three others] |
| Autore | Gallardo S. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 |
| Descrizione fisica | 1 online resource (1 volume (various pagings)) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Computer programs Nuclear power plants - Accidents Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Simulation of ROSA-2 test-2 experiment |
| Record Nr. | UNINA-9910712078503321 |
Gallardo S.
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 | ||
| Lo trovi qui: Univ. Federico II | ||
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Spatial effects and uncertainty analysis for rod ejection accidents in a PWR / / prepared by A. Avvakumov, V. Malofeev, V. Sidorov
| Spatial effects and uncertainty analysis for rod ejection accidents in a PWR / / 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, , September 2007 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors
Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698138303321 |
Avvakumov A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 2007 | ||
| Lo trovi qui: Univ. Federico II | ||
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