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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.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Effect of LWR water environments on the fatigue life of reactor materials : final report / / prepared by Omesh Chopra and Gary L. Stevens
| Effect of LWR water environments on the fatigue life of reactor materials : final report / / prepared by Omesh Chopra and Gary L. Stevens |
| Autore | Chopra O. K. |
| Edizione | [Rev. 1.] |
| Pubbl/distr/stampa | [Washington, D.C.] : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , May 2018 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations (chiefly color) |
| Soggetto topico |
Light water reactors - Materials - Deterioration
Nuclear engineering - Materials |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Effect of LWR water environments on the fatigue life of reactor materials |
| Record Nr. | UNINA-9910709872803321 |
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Chopra O. K.
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| [Washington, D.C.] : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , May 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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 |
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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 | ||
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