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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.
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| 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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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.
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| 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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Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments [[electronic resource] /] / prepared by Y. Chen ... [and others]
| Irradiation-assisted stress corrosion cracking of austenitic stainless steels in BWR environments [[electronic resource] /] / prepared by Y. Chen ... [and others] |
| Pubbl/distr/stampa | [Washington, DC] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (xxiv, 89 pages) : illustrations (some color) |
| Altri autori (Persone) | ChenY |
| Soggetto topico |
Boiling water reactors - Materials - Stress corrosion
Stainless steel - Stress corrosion |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699326603321 |
| [Washington, DC] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Pacific Northwest National Laboratory investigation of stress corrosion cracking in nickel-base alloys / / prepared by S.M. Bruemmer [and others]
| Pacific Northwest National Laboratory investigation of stress corrosion cracking in nickel-base alloys / / prepared by S.M. Bruemmer [and others] |
| Pubbl/distr/stampa | Washington, D.C., : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research., [2011-2019] |
| Descrizione fisica | 1 online resource (4 volumes) : color illustrations |
| Altri autori (Persone) | BruemmerS. M |
| Soggetto topico |
Stainless steel - Stress corrosion
Nuclear power plants - Materials - Testing Nickel alloys |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti |
Stress corrosion cracking of cold worked alloy 690
Behavior of alloy 52 and 152 welds |
| Record Nr. | UNINA-9910701325403321 |
| Washington, D.C., : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research., [2011-2019] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Stress corrosion cracking in nonsensitized 316 stainless steel
| Stress corrosion cracking in nonsensitized 316 stainless steel |
| 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 |
Stainless steel - Stress corrosion
Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910714096803321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1984 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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