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Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar
| Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar |
| Autore | Oussoren Andrew |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 |
| Descrizione fisica | 1 online resource (xv, 29 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear power plants - Piping - Cracking |
| Soggetto genere / forma | Online resources. |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706176303321 |
Oussoren Andrew
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components [[electronic resource] /] / prepared by A.A. Diaz ... [and others]
| Assessment of eddy current testing for the detection of cracks in cast stainless steel reactor piping components [[electronic resource] /] / prepared by A.A. Diaz ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2007 |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | DiazAaron A |
| Soggetto topico | Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697847003321 |
| Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Division of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2007 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Axial (longitudinal) oriented cracking in piping
| Axial (longitudinal) oriented cracking in piping |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1980 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico | Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Axial |
| Record Nr. | UNINA-9910711756503321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Circumferential cracking of steam generator tubes
| Circumferential cracking of steam generator tubes |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1995 |
| Descrizione fisica | 1 online resource |
| Collana | NRC generic letter |
| Soggetto topico |
Steam-pipes - Cracking
Pressurized water reactors - Materials - Cracking Nuclear power plants - Piping - Cracking |
| Soggetto genere / forma | Online resources. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711441903321 |
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1995 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Cracking in main steam lines
| Cracking in main steam lines |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1981 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Steam-pipes - Cracking
Pressurized water reactors - Materials - Cracking Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910713068003321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Cracks in stiffening rings on 48-Inch-diameter UF6 cylinders
| Cracks in stiffening rings on 48-Inch-diameter UF6 cylinders |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , 1987 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Nuclear power plants - Piping - Cracking
Cylinders - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715128403321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , 1987 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Degradation of containment isolation capability by a high-energy line break
| Degradation of containment isolation capability by a high-energy line break |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1989 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Nuclear reactors - Containment
Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715397003321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1989 | ||
| 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
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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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Fatigue crack flaw tolerance in nuclear power plant piping [[electronic resource] ] : a basis for improvements to ASME code section XI Appendix L / / S.R. Gosselin ... [and others]
| Fatigue crack flaw tolerance in nuclear power plant piping [[electronic resource] ] : a basis for improvements to ASME code section XI Appendix L / / S.R. Gosselin ... [and others] |
| 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 | 131 unnumbered pages : digital, PDF file |
| Altri autori (Persone) | GosselinS. R |
| Soggetto topico |
Nuclear power plants - Piping - Fatigue
Nuclear power plants - Piping - Cracking |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Fatigue crack flaw tolerance in nuclear power plant piping |
| Record Nr. | UNINA-9910697384303321 |
| 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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IGSCC in BWR plants
| IGSCC in BWR plants |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1984 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Boiling water reactors
Nuclear power plants - Piping - Cracking Nuclear power plants - Piping - Corrosion |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Intergranular stress corrosion cracking in boiling water reactor plants |
| Record Nr. | UNINA-9910713913903321 |
| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Inspection and Enforcement, , 1984 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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