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Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak
| Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
| Autore | Belaïd S. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (xiii, 29 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement Nuclear fuel claddings - Effect of temperature on - Measurement Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE |
| Record Nr. | UNINA-9910704812803321 |
Belaïd S.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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BWR anticipated transients without scram in the MELLLA+ expanded operating domain / / Lap-Yan Cheng [and five others]
| BWR anticipated transients without scram in the MELLLA+ expanded operating domain / / Lap-Yan Cheng [and five others] |
| Autore | Cheng Lap-Yan |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , June 2015 |
| Descrizione fisica | 1 online resource (4 volumes) : color illustrations |
| Soggetto topico |
Boiling water reactors - Performance - Testing - Computer simulation
Boiling water reactors - Performance - Technological innovations Nuclear power plants - Safety measures - Computer programs Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Part 1 : Model development and events leading to instability -- Part 2 : Sensitivity studies for events leading to instability -- Part 3 : Events leading to emergency depressurization -- Part 4 : Sensitivity studies for events leading to emergency depressurization. |
| Altri titoli varianti | Boiling Water Reactor anticipated transients without scram in the MELLLA+ expanded operating domain |
| Record Nr. | UNINA-9910703879703321 |
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Cheng Lap-Yan
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| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , June 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Draft regulatory guide DG-1187 [[electronic resource] ] : concrete radiation shields and generic shield testing for nuclear power plants
| Draft regulatory guide DG-1187 [[electronic resource] ] : concrete radiation shields and generic shield testing for nuclear power plants |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] |
| Descrizione fisica | 6 pages : digital, PDF file |
| Collana | Draft regulatory guide |
| Soggetto topico |
Nuclear reactors - Shielding (Radiation) - Testing
Concrete - Testing Nuclear power plants - Safety measures - Testing Nuclear power plants - Standards |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Draft regulatory guide DG-1187 |
| Record Nr. | UNINA-9910697820703321 |
| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Draft Regulatory Guide DG-1203 [[electronic resource] ] : containment performance for pressure loads
| Draft Regulatory Guide DG-1203 [[electronic resource] ] : containment performance for pressure loads |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] |
| Descrizione fisica | 21 pages : digital, PDF file |
| Soggetto topico |
Nuclear power plants - Safety measures - Standards
Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Draft Regulatory Guide DG-1203 |
| Record Nr. | UNINA-9910697824403321 |
| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Draft Regulatory Guide DG-1205 [[electronic resource] ] : bypassed and inoperable status indication for nuclear power plant safety systems
| Draft Regulatory Guide DG-1205 [[electronic resource] ] : bypassed and inoperable status indication for nuclear power plant safety systems |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] |
| Descrizione fisica | 10 pages : digital, PDF file |
| Soggetto topico |
Nuclear power plants - Safety measures - Standards
Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Draft Regulatory Guide DG-1205 |
| Record Nr. | UNINA-9910697824003321 |
| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Inadequate testing of engineered safety features actuation systems [[electronic resource]]
| Inadequate testing of engineered safety features actuation systems [[electronic resource]] |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1993] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico | Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701824403321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1993] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Performance of metal and polymeric o-ring seals in beyond-design-basis temperature excursions [[electronic resource] /] / prepared by Jiann C. Yang, Edward J. Hnetkovsky
| Performance of metal and polymeric o-ring seals in beyond-design-basis temperature excursions [[electronic resource] /] / prepared by Jiann C. Yang, Edward J. Hnetkovsky |
| Autore | Yang Jiann C (Jiann Chyuan) |
| Pubbl/distr/stampa | Washington, DC, : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, November 2015 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Altri autori (Persone) | HnetkovskyEdward J |
| Soggetto topico |
O-rings - Effect of temperature on - Testing
Sealing (Technology) - Equipment and supplies - Testing Nuclear power plants - Safety measures - Testing Nuclear facilities - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701943903321 |
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Yang Jiann C (Jiann Chyuan)
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| Washington, DC, : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, November 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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