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.
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 | ||
| ||
Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests / / prepared by E.J. Stubbe, L. Vanhoenacker
| Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests / / prepared by E.J. Stubbe, L. Vanhoenacker |
| Autore | Stubbe E. J (Elie J.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1990 |
| Descrizione fisica | 1 online resource (37 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Safety measures - Simulation methods
Relief valves - Testing Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707626103321 |
|
Stubbe E. J (Elie J.)
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads / / prepared by E.J. Stubbe, L. VanHoenacker, R. Otero
| RELAP5/MOD3 assessment for calculation of safety and relief valve discharge piping hydrodynamic loads / / prepared by E.J. Stubbe, L. VanHoenacker, R. Otero |
| Autore | Stubbe E. J (Elie J.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 1994 |
| Descrizione fisica | 1 online resource (24 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Piping - Valves - Testing - Data processing
Relief valves - Testing - Data processing Pressurized water reactors - Safety measures - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708489803321 |
|
Stubbe E. J (Elie J.)
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 1994 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||