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.
Crack growth rate and fracture toughness tests on irradiated cast stainless steels / / prepared by Y. Chen, B. Alexandreanu, and K. Natesan
| Crack growth rate and fracture toughness tests on irradiated cast stainless steels / / prepared by Y. Chen, B. Alexandreanu, and K. Natesan |
| Autore | Chen Y. |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , July 2015 |
| Descrizione fisica | 1 online resource (181 unnumbered pages) : color illustrations |
| Soggetto topico |
Austenitic stainless steel - Cracking - Testing
Light water reactors - Cooling Stainless steel - Stress corrosion Stress corrosion - Testing Neutron irradiation Stainless steel - Welding Stainless steel - Fracture |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703840603321 |
Chen Y.
|
||
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , July 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Effect of LWR coolant environments on the fatigue life of reactor materials : draft report for comment / / prepared by Omesh Chopra and Gary L. Stevens
| Effect of LWR coolant environments on the fatigue life of reactor materials : draft report for comment / / prepared by Omesh Chopra and Gary L. Stevens |
| Autore | Chopra O. K. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 |
| Descrizione fisica | 1 online resource (325 unnumbered pages) : color illustrations |
| Soggetto topico |
Nuclear reactors - Materials - Fatigue
Light water reactors - Cooling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Effect of LWR coolant environments on the fatigue life of reactor materials |
| Record Nr. | UNINA-9910705202503321 |
|
Chopra O. K.
|
||
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Effect of LWR coolant environments on the fatigue life of reactor materials [[electronic resource] ] : final report / / prepared by O.K. Chopra and W.J. Shack
| Effect of LWR coolant environments on the fatigue life of reactor materials [[electronic resource] ] : final report / / prepared by O.K. Chopra and W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering, and Radiological Research, , [2007] |
| Descrizione fisica | 1 online resource (121 unnumbered pages) : color illustrations |
| Altri autori (Persone) | ShackW. J |
| Soggetto topico |
Nuclear reactors - Materials - Fatigue
Light water reactors - Cooling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Effect of LWR coolant environments on the fatigue life of reactor materials |
| Record Nr. | UNINA-9910697389503321 |
|
Chopra O. K
|
||
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering, and Radiological Research, , [2007] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Effect of thermal aging and neutron irradiation on crack growth rate and fracture toughness of cast stainless steels and austenitic stainless steel welds / / prepared by Omesh K. Chopra
| Effect of thermal aging and neutron irradiation on crack growth rate and fracture toughness of cast stainless steels and austenitic stainless steel welds / / prepared by Omesh K. Chopra |
| Autore | Chopra O. K. |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , July 2015 |
| Descrizione fisica | 1 online resource (173 unnumbered pages) : color illustrations |
| Soggetto topico |
Austenitic stainless steel - Cracking - Testing
Stainless steel - Stress corrosion Stress corrosion - Testing Neutron irradiation Stainless steel - Welding Stainless steel - Fracture Light water reactors - Cooling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703840803321 |
|
Chopra O. K.
|
||
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , July 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
