top

  Info

  • Utilizzare la checkbox di selezione a fianco di ciascun documento per attivare le funzionalità di stampa, invio email, download nei formati disponibili del (i) record.

  Info

  • Utilizzare questo link per rimuovere la selezione effettuata.
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
Chopra O. K  
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
Opac: Controlla la disponibilità qui
Environmental effects on fatigue crack initiation in piping and pressure vessel steels [[electronic resource] /] / prepared by O.K. Chopra, W.J. Shack
Environmental effects on fatigue crack initiation in piping and pressure vessel steels [[electronic resource] /] / prepared by O.K. Chopra, 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, , 2001
Descrizione fisica xvi, 68 pages : digital, PDF file
Altri autori (Persone) ShackW. J
Soggetto topico Steel alloys - Fatigue
Steel - Fatigue
Pipe, Steel - Fatigue
Nuclear pressure vessels - Materials - Fatigue
Light water reactors - Materials - Fatigue
Nuclear power plants - Piping - Cracking
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910698568103321
Chopra O. K  
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2001
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems [[electronic resource] /] / prepared by O.K. Chopra, A. Sather
Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems [[electronic resource] /] / prepared by O.K. Chopra, A. Sather
Autore Chopra O. K
Pubbl/distr/stampa Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1990
Descrizione fisica 1 volume (various pagings) : digital, PDF file
Altri autori (Persone) SatherA
Soggetto topico Steel, Cast - Effect of temperature on - Testing
Light water reactors - Materials - Fatigue
Stainless steel - Fatigue
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910697212103321
Chopra O. K  
Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1990
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments [[electronic resource] /] / prepared by O.K. Chopra
Mechanism and estimation of fatigue crack initiation in austenitic stainless steels in LWR environments [[electronic resource] /] / prepared by O.K. Chopra
Autore Chopra O. K
Pubbl/distr/stampa Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2002
Descrizione fisica xvi, 64 pages : digital, PDF file
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-9910698567103321
Chopra O. K  
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2002
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui