Info
- Utilizzare la checkbox di selezione a fianco di ciascun documento per attivare le funzionalità di stampa, invio email, download nei formati disponibili del (i) record.
Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports"
| Additional guidance on "Potential for low fracture toughness and lamellar tearing on PWR steam generator and reactor coolant pump supports" |
| Pubbl/distr/stampa | [Washington, D.C ] : , : [U.S. Nuclear Regulatory Commission], , 1980 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Pressurized water reactors
Nuclear reactors - Materials - Testing |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Additional guidance on "Potential for low fracture toughness and lamellar tearing on pressurized water reactor steam generator and reactor coolant pump supports" |
| Record Nr. | UNINA-9910715953203321 |
| [Washington, D.C ] : , : [U.S. Nuclear Regulatory Commission], , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
An approach for estimating the frequencies of various containment failure modes and bypass events [[microform] ] : final report / / prepared by W.T. Pratt ... [and others]
| An approach for estimating the frequencies of various containment failure modes and bypass events [[microform] ] : final report / / prepared by W.T. Pratt ... [and others] |
| Edizione | [Rev 1.] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2004 |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | PrattW. T (William T.) |
| Soggetto topico |
Nuclear reactors - Containment
Nuclear power plants - Risk assessment Pressurized water reactors |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Approach for estimating the frequencies of various containment failure modes and bypass events |
| Record Nr. | UNINA-9910697395803321 |
| Washington, DC : , : Division of Risk Analysis and Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2004 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assessment study of RELAP-5 MOD-2 cycle 36.01 : based on the Doel-2 steam generator tube rupture incident of June 1979 / / prepared by E. J. Stubbe
| Assessment study of RELAP-5 MOD-2 cycle 36.01 : based on the Doel-2 steam generator tube rupture incident of June 1979 / / prepared by E. J. Stubbe |
| Autore | Stubbe E. J (Elie J.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1986 |
| Descrizione fisica | 1 online resource (v, 232 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Tubes - Defects
Tubes - Corrosion Pressurized water reactors |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment study of RELAP-5 MOD-2 cycle 36.01 |
| Record Nr. | UNINA-9910707645503321 |
Stubbe E. J (Elie J.)
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Assurance of sufficient net positive suction head for emergency core cooling and containment heat removal pumps [[electronic resource]]
| Assurance of sufficient net positive suction head for emergency core cooling and containment heat removal pumps [[electronic resource]] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] |
| Descrizione fisica | 1 online resource |
| Collana | NRC generic letter |
| Soggetto topico |
Pumping machinery - Motors - Valves - Analysis
Pressurized water reactors Emergency core cooling systems Nuclear reactors - Containment |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699545803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Auxiliary feedwater sparger and pipe hanger damage
| Auxiliary feedwater sparger and pipe hanger damage |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1984 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Pressurized water reactors
Feed-water |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910713919003321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1984 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / / prepared by D.E. Mueller [and three others]
| Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / / prepared by D.E. Mueller [and three others] |
| Autore | Mueller D. E. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , September 2015 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Soggetto topico |
Fission products - Handling
Monte Carlo method Actinide elements Fuel burnup (Nuclear engineering) Spent reactor fuels - Storage Spent reactor fuels - Transportation Pressurized water reactors |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698624303321 |
|
Mueller D. E.
|
||
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , September 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Complete loss of main and auxiliary feedwater at a PWR designed by Babcock & Wilcox
| Complete loss of main and auxiliary feedwater at a PWR designed by Babcock & Wilcox |
| 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 |
Pressurized water reactors
Feed-water Feed-water pumps |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Complete loss of main and auxiliary feedwater at a pressurized water reactor designed by Babcock & Wilcox |
| Record Nr. | UNINA-9910714059103321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1985 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS
| Control rod drive (CRD) guide tube support pin failures at Westinghouse PWRS |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1982 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Pressurized water reactors
Nuclear reactors - Control |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Control rod drive |
| Record Nr. | UNINA-9910713804803321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1982 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Coolant chemistry control and effects on fuel reliability in pressurized heavy water reactors : report of a technical meeting / / IAEA
| Coolant chemistry control and effects on fuel reliability in pressurized heavy water reactors : report of a technical meeting / / IAEA |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2021] |
| Descrizione fisica | 1 online resource (128 pages) |
| Disciplina | 621.48336 |
| Collana | IAEA TECDOC Series |
| Soggetto topico | Pressurized water reactors |
| ISBN |
92-0-133821-X
1-5231-4993-0 1-5231-4994-9 92-0-133921-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910794416603321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2021] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Coolant chemistry control and effects on fuel reliability in pressurized heavy water reactors : report of a technical meeting / / IAEA
| Coolant chemistry control and effects on fuel reliability in pressurized heavy water reactors : report of a technical meeting / / IAEA |
| Edizione | [1st ed.] |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2021] |
| Descrizione fisica | 1 online resource (128 pages) |
| Disciplina | 621.48336 |
| Collana | IAEA TECDOC Series |
| Soggetto topico | Pressurized water reactors |
| ISBN |
92-0-133821-X
1-5231-4993-0 1-5231-4994-9 92-0-133921-6 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910822231403321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2021] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
