Assessment of void swelling in austenitic stainless steel core internals [[electronic resource] /] / prepared by H.M. Chung |
Autore | Chung H. M |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 |
Descrizione fisica | xiv, 24 pages : digital, PDF file |
Soggetto topico |
Nuclear reactors - Cores - Materials - Expansion and contraction
Austenitic stainless steel - Expansion and contraction |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910697304603321 |
Chung H. M | ||
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Irradiation-assisted stress corrosion cracking behavior of austenitic stainless steels applicable to LWR core internals [[electronic resource] /] / prepared by H.M. Chung, W.J. Shack |
Autore | Chung H. M |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 |
Descrizione fisica | xxii, 98 pages : digital, PDF file |
Altri autori (Persone) | ShackW. J |
Soggetto topico |
Light water reactors - Materials - Stress corrosion
Austenitic stainless steel - Stress corrosion |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910698544303321 |
Chung H. M | ||
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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