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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 material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments [[electronic resource] /] / prepared by O.K. Chopra, B. Alexandreanu, and W.J. Shack
| Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments [[electronic resource] /] / prepared by O.K. Chopra, B. Alexandreanu, and W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2005] |
| Descrizione fisica | xviii, 44 pages : digital, PDF file |
| Altri autori (Persone) |
AlexandreanuB
ShackW. J |
| Soggetto topico |
Austenitic stainless steel - Fatigue
Light water reactors - Materials - Fatigue |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698545003321 |
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Chopra O. K
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| Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2005] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Stress corrosion cracking in nickel-base alloys 690 and 152 weld in simulated PWR environment - 2009 [[electronic resource] /] / prepared by B. Alexandeanu
| Stress corrosion cracking in nickel-base alloys 690 and 152 weld in simulated PWR environment - 2009 [[electronic resource] /] / prepared by B. Alexandeanu |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, , [2012] |
| Descrizione fisica | 1 online resource (136 unnumbered pages) : color illustrations |
| Altri autori (Persone) | AlexandreanuB |
| Soggetto topico |
Pressurized water reactors - Welding - Testing
Nickel alloys - Welding - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702310303321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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