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. | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 | ||
Materiale a stampa | ||
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 |
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 | ||
Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2003 | ||
Materiale a stampa | ||
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 |
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 | ||
Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
|
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] | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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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 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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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 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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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. | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 | ||
Materiale a stampa | ||
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] |
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] | ||
Materiale a stampa | ||
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] |
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. | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 | ||
Materiale a stampa | ||
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 |
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. | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 2007 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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