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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.  
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
Opac: Controlla la disponibilità qui
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  
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
Opac: Controlla la disponibilità qui
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  
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
Opac: Controlla la disponibilità qui
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]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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.  
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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.  
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
Opac: Controlla la disponibilità qui
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.  
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 2007
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui

Data di pubblicazione