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Assessment study of RELAP-5 MOD-2 cycle 36.01 : based on the Doel-2 steam generator tube rupture incident of June 1979 / / prepared by E. J. Stubbe
| Assessment study of RELAP-5 MOD-2 cycle 36.01 : based on the Doel-2 steam generator tube rupture incident of June 1979 / / prepared by E. J. Stubbe |
| Autore | Stubbe E. J (Elie J.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1986 |
| Descrizione fisica | 1 online resource (v, 232 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Tubes - Defects
Tubes - Corrosion Pressurized water reactors |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment study of RELAP-5 MOD-2 cycle 36.01 |
| Record Nr. | UNINA-9910707645503321 |
Stubbe E. J (Elie J.)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1986 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Failure of primary system compression fitting
| Failure of primary system compression fitting |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1992] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Pressurized water reactors - United States - Loss of coolant
Tubes - Defects |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707207603321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1992] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Steam generator tube rupture analysis deficiency
| Steam generator tube rupture analysis deficiency |
| Pubbl/distr/stampa | Washington, D.C. : , : United States. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1988 |
| Descrizione fisica | 1 online resource |
| Collana | Information notice |
| Soggetto topico |
Steam-boilers - Failures
Tubes - Defects |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715285303321 |
| Washington, D.C. : , : United States. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1988 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Voltage based repair criteria for Westinghouse steam generator tubes affected by outside diameter stress corrosion cracking
| Voltage based repair criteria for Westinghouse steam generator tubes affected by outside diameter stress corrosion cracking |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1995 |
| Descrizione fisica | 1 online resource |
| Collana | NRC generic letter |
| Soggetto topico |
Tubes - Defects
Steam-boilers - Deterioration Pressurized water reactors - Deterioration |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711441703321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , 1995 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Voltage-based alternative repair criteria : a report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion
| Voltage-based alternative repair criteria : a report to the Advisory Committee on Reactor Safeguards by the Ad Hoc Subcommittee on a Differing Professional Opinion |
| Pubbl/distr/stampa | Washington, DC : , : Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, , March 2001 |
| Descrizione fisica | 1 online resource (viii, 51, 6 unnumbered pages) : illustrations |
| Soggetto topico |
Tubes - Defects
Steam-boilers - Deterioration Pressurized water reactors - Deterioration |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Voltage-based alternative repair criteria |
| Record Nr. | UNINA-9910708659303321 |
| Washington, DC : , : Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, , March 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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