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Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments [[electronic resource] /] / prepared by O.K. Chopra and W.J. Shack
| Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments [[electronic resource] /] / prepared by O.K. Chopra and W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | ShackW. J |
| Soggetto topico |
Nuclear power plants - Fracture
Austenitic stainless steel - Fracture Fracture mechanics |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698467503321 |
Chopra O. K
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| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Degradation of LWR core internal materials due to neutron irradiation [[electronic resource] /] / prepared by O.K. Chopra
| Degradation of LWR core internal materials due to neutron irradiation [[electronic resource] /] / prepared by O.K. Chopra |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (xxviii, 122 pages) : color illustrations |
| Soggetto topico |
Light water reactors
Neutron irradiation Nuclear reactors - Cores |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Degradation of light water reactor core internal materials due to neutron irradiation |
| Record Nr. | UNINA-9910700382403321 |
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Chopra O. K
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| 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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Effect of LWR coolant environments on the fatigue life of reactor materials [[electronic resource] ] : final report / / prepared by O.K. Chopra and W.J. Shack
| Effect of LWR coolant environments on the fatigue life of reactor materials [[electronic resource] ] : final report / / prepared by O.K. Chopra and W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering, and Radiological Research, , [2007] |
| Descrizione fisica | 1 online resource (121 unnumbered pages) : color illustrations |
| Altri autori (Persone) | ShackW. J |
| Soggetto topico |
Nuclear reactors - Materials - Fatigue
Light water reactors - Cooling |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Effect of LWR coolant environments on the fatigue life of reactor materials |
| Record Nr. | UNINA-9910697389503321 |
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Chopra O. K
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering, and Radiological Research, , [2007] | ||
| 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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Effects of alloy chemistry, cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds [[electronic resource] /] / O.K. Chopra, W.K. Soppet, W.J. Shack
| Effects of alloy chemistry, cold work, and water chemistry on corrosion fatigue and stress corrosion cracking of nickel alloys and welds [[electronic resource] /] / O.K. Chopra, W.K. Soppet, 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 | xii, 50 pages : digital, PDF file |
| Altri autori (Persone) |
SoppetW. K
ShackW. J |
| Soggetto topico |
Nickel alloys - Corrosion fatigue
Nickel alloys - Stress corrosion Light water reactors - Materials - Corrosion fatigue Light water reactors - Materials - Stress corrosion |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698568503321 |
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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, , 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels [[electronic resource] /] / prepared by O.K. Chopra
| Effects of LWR coolant environments on fatigue design curves of austenitic stainless steels [[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, , 1999 |
| Descrizione fisica | xii pages, 42 unnumbered pages : digital, PDF file |
| Soggetto topico |
Austenitic stainless steel - Fatigue
Light water reactors - Materials |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697210503321 |
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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, , 1999 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels [[microform] /] / prepared by O.K. Chopra, W.J. Shack
| Effects of LWR coolant environments on fatigue design curves of carbon and low-alloy steels [[microform] /] / prepared by O.K. Chopra, W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 1998 |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | ShackW. J |
| Soggetto topico |
Nuclear reactors - Safety measures
Light water reactors - Safety measures Steel alloys - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698568403321 |
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Chopra O. K
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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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 |
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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 | ||
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Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems [[electronic resource] /] / prepared by O.K. Chopra
| Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems [[electronic resource] /] / prepared by O.K. Chopra |
| Autore | Chopra O. K |
| Edizione | [Rev. 1.] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1994 |
| Descrizione fisica | xiii, 54, 12 pages : digital, PDF file |
| Soggetto topico |
Stainless steel - Effect of temperature on
Stainless steel - Embrittlement Light water reactors - Materials - Effect of temperature on Light water reactors - Materials - Embrittlement |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698568003321 |
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Chopra O. K
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1994 | ||
| 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
| 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 |
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Chopra O. K
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| 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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