Degradation of steam generator internals |
Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] |
Descrizione fisica | 1 online resource (7 pages) |
Collana | NRC generic letter |
Soggetto topico |
Nuclear power plants - Piping - Deterioration
Steam-pipes - Deterioration |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910699545503321 |
Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1997] | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Fracture toughness and crack growth rates of irradiated austenitic stainless steels [[electronic resource] /] / prepared by O.K. Chopra, E.E. Gruber, W.J. Shack |
Autore | Chopra O. K |
Pubbl/distr/stampa | Washington, D.C. : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2003 |
Descrizione fisica | xvi, 86 pages : digital, PDF file |
Altri autori (Persone) |
GruberE. E <1933-> (Eugene E.)
ShackW. J |
Soggetto topico |
Nuclear power plants - Piping - Deterioration
Austenitic stainless steel - Fracture Fracture mechanics |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910693968703321 |
Chopra O. K | ||
Washington, D.C. : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2003 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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