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Application of automated analysis software to eddy current inspection data from steam generator tube bundle mock-up / / S. Bakhtiari, W.J. Shack and T.W. Elmer
| Application of automated analysis software to eddy current inspection data from steam generator tube bundle mock-up / / S. Bakhtiari, W.J. Shack and T.W. Elmer |
| Autore | Bakhtiari Sasan |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , September 2016 |
| Descrizione fisica | 1 online resource (xxv, 137 pages) : illustrations |
| Soggetto topico |
Eddy currents (Electric) - Data processing
Steam-boiler inspection - Data processing Steam-boiler inspection |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707643103321 |
Bakhtiari Sasan
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , September 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Application of model abstraction techniques to simulate transport in soils [[electronic resource] /] / prepared by Y. Pachepsky ... [and others]
| Application of model abstraction techniques to simulate transport in soils [[electronic resource] /] / prepared by Y. Pachepsky ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (214 unnumbered pages) : color illustrations |
| Altri autori (Persone) | PachepskyY (Yakov) |
| Soggetto topico |
Radioactive pollution of soils - Models
Radioactive pollution of water - Models Radioactive tracers in water pollution research |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910700375703321 |
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Application of point precipitation frequency estimates to watersheds / / prepared by Shih-Chieh Kao, Scott T. DeNeale
| Application of point precipitation frequency estimates to watersheds / / prepared by Shih-Chieh Kao, Scott T. DeNeale |
| Autore | Gao Shijie |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , February 2021 |
| Descrizione fisica | 1 online resource (approximately 179 pages) : illustrations (Chiefly color), color maps |
| Soggetto topico |
Precipitation (Meteorology) - United States - Mathematical models
Rain and rainfall - United States - Mathematical models Runoff - United States - Mathematical models |
| Soggetto genere / forma | Technical reports. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910716651303321 |
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Gao Shijie
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , February 2021 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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An approach for validating actinide and fission product burnup credit criticality safety analyses--isotopic composition predictions / / prepared by G. Radulescu [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
| An approach for validating actinide and fission product burnup credit criticality safety analyses--isotopic composition predictions / / prepared by G. Radulescu [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
| Autore | Radulescu G. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2012 |
| Descrizione fisica | 1 online resource (113 unnumbered pages) : color illustrations |
| Soggetto topico |
Fuel burnup (Nuclear engineering) - Models - United States
Fuel burnup (Nuclear engineering) - Measurement Nuclear fuels - Safety measures - Standards Spent reactor fuels - Safety measures - Standards - United States Nuclear reactors - United States - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708119303321 |
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Radulescu G.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2012 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessing the potential for biorestoration of uranium in situ recovery sites / / prepared by S.B. Yabusaki [and six others]
| Assessing the potential for biorestoration of uranium in situ recovery sites / / prepared by S.B. Yabusaki [and six others] |
| Autore | Yabusaki S. B. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , June 2014 |
| Descrizione fisica | 1 online resource (263 unnumbered pages) : color illustrations |
| Soggetto topico |
In situ bioremediation
Uranium Radioactive waste sites - Cleanup |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702410103321 |
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Yabusaki S. B.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , June 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Atmospheric stress corrosion cracking susceptibility of welded and unwelded 304, 304L, and 316L austenitic stainless steels commonly used for dry cask storage containers exposed to marine environments [[electronic resource] /] / preapred by L. Caseres and T. S. Mintz
| Atmospheric stress corrosion cracking susceptibility of welded and unwelded 304, 304L, and 316L austenitic stainless steels commonly used for dry cask storage containers exposed to marine environments [[electronic resource] /] / preapred by L. Caseres and T. S. Mintz |
| Autore | Caseres L |
| Pubbl/distr/stampa | San Antonio, TX : , : Southwest Research Institute |
| Descrizione fisica | 1 online resource (xviii, 66 pages) : digital, PDF file |
| Altri autori (Persone) | MintzT. S (Todd S.) |
| Soggetto topico |
Radioactive waste canisters
Austenitic stainless steel |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699719203321 |
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Caseres L
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| San Antonio, TX : , : Southwest Research Institute | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit / / prepared by William (B.J.) Marshall [and three others]
| Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit / / prepared by William (B.J.) Marshall [and three others] |
| Autore | Marshall William (William B. J.) |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , August 2016 |
| Descrizione fisica | 1 online resource (xi, 99, A4 pages) : color illustrations |
| Soggetto topico |
Boiling water reactors
Spent reactor fuels - Storage Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707689303321 |
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Marshall William (William B. J.)
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , August 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Basis for the treatment of potential common cause failure in the significance determination process
| Basis for the treatment of potential common cause failure in the significance determination process |
| Pubbl/distr/stampa | Washington, D.C, : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910712656803321 |
| Washington, D.C, : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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The Browns Ferry Nuclear Plant fire of 1975 and the history of NRC fire regulations
| The Browns Ferry Nuclear Plant fire of 1975 and the history of NRC fire regulations |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2009 |
| Descrizione fisica | 1 online resource (8 pages) : illustrations (some color) |
| Collana | NUREG/BR |
| Soggetto topico |
Nuclear power plants - Fires and fire prevention - Alabama
Nuclear power plants - Accidents - Alabama |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
Browns Ferry Nuclear Plant fire of 1975 and the history of Nuclear Regulatory Commission fire regulations
Protecting people and the environment |
| Record Nr. | UNINA-9910705710203321 |
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2009 | ||
| 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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