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2D/3D Program work summary report / / edited by P.S. Damerell, J. W. Simons
| 2D/3D Program work summary report / / edited by P.S. Damerell, J. W. Simons |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana |
GRS
International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Pressurized water reactors - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707866403321 |
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Actuation of ECCS in the recirculation mode while in hot shutdown
| Actuation of ECCS in the recirculation mode while in hot shutdown |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1980 |
| Descrizione fisica | 1 online resource (2 pages) |
| Collana | Information notice |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Emergency core cooling systems Nuclear reactors - Shutdown |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Actuation of emergency core cooling system in the recirculation mode while in hot shutdown |
| Record Nr. | UNINA-9910711734103321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Aluminum chemistry in a prototypical post-loss-of-coolant-accident, pressurized-water-reactor containment environment [[electronic resource] /] / principal investigator, M. Klasky ; prepared by M. Klasky ... [and others]
| Aluminum chemistry in a prototypical post-loss-of-coolant-accident, pressurized-water-reactor containment environment [[electronic resource] /] / principal investigator, M. Klasky ; prepared by M. Klasky ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 |
| Descrizione fisica | xviii, 92 pages : digital, PDF file |
| Altri autori (Persone) | KlaskyM |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear reactors - Containment - Materials |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697834603321 |
| Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Application of RELAP5/MOD3.1 code to the LOFT test L3-6 / / prepared by S.S. Pylev and V.L. Roginskaja
| Application of RELAP5/MOD3.1 code to the LOFT test L3-6 / / prepared by S.S. Pylev and V.L. Roginskaja |
| Autore | Pylev S. S (Stanislav Semenovich) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 1998 |
| Descrizione fisica | 1 online resource (62 pages) : illustrations, maps |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility)
Pressurized water reactors - Loss of coolant |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707644803321 |
Pylev S. S (Stanislav Semenovich)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar
| Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar |
| Autore | Oussoren Andrew |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 |
| Descrizione fisica | 1 online resource (xv, 29 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear power plants - Piping - Cracking |
| Soggetto genere / forma | Online resources. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706176303321 |
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Oussoren Andrew
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Asymmetric blowdown loads on PWR primary systems : resolution of generic task action plan A-2 / / S.B. Hosford [and four others]
| Asymmetric blowdown loads on PWR primary systems : resolution of generic task action plan A-2 / / S.B. Hosford [and four others] |
| Autore | Hosford S. B (Steve B.) |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , 1981 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico | Pressurized water reactors - Loss of coolant |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Asymmetric blowdown loads on PWR primary systems |
| Record Nr. | UNINA-9910705602103321 |
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Hosford S. B (Steve B.)
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| Washington, D.C. : , : Division of Safety Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Audit of small break LOCA guidelines
| Audit of small break LOCA guidelines |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear power plants - Accidents
Boiling water reactors - Loss of coolant Pressurized water reactors - Loss of coolant |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Audit of small break loss of coolant accident guidelines |
| Record Nr. | UNINA-9910715976303321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós
| Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 |
| Descrizione fisica | 1 online resource (xvii, 30 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear reactors - Cores |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Core exit temperature response during an Small Break LOss of Coolant Acicident event in the Ascó Nuclear Power Plant |
| Record Nr. | UNINA-9910711961103321 |
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Freixa J.
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| Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Degaded throttle valves in emergency core cooling system resulting from cavitation-induced erosion during a loss-of-coolant accident [[electronic resource]]
| Degaded throttle valves in emergency core cooling system resulting from cavitation-induced erosion during a loss-of-coolant accident [[electronic resource]] |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Pressurized water reactors
Emergency core cooling systems Pressurized water reactors - Loss of coolant |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699754103321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Depressurization of reactor coolant systems in pressurized-water reactors
| Depressurization of reactor coolant systems in pressurized-water reactors |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1987 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear reactors - Cooling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715115103321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1987 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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