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Review and assessment of codes and procedures for HTGR components [[electronic resource] /] / prepared by V.N. Shah, S. Majumdar, K. Natesan
| Review and assessment of codes and procedures for HTGR components [[electronic resource] /] / prepared by V.N. Shah, S. Majumdar, K. Natesan |
| Autore | Shah Vikram N |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2003 |
| Descrizione fisica | xvi, 63 pages : digital, PDF file |
| Altri autori (Persone) |
MajumdarS (Saurindranath)
NatesanK <1942-> (Krishnamurti) |
| Soggetto topico | Gas cooled reactors - Design and construction - Standards |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697356503321 |
Shah Vikram N
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| Washington, DC : , : 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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Sensitivity studies of failure of steam generator tubes during main steam line break and other secondary side depressurization events [[electronic resource] /] / prepared by S. Majumdar ... [and others]
| Sensitivity studies of failure of steam generator tubes during main steam line break and other secondary side depressurization events [[electronic resource] /] / prepared by S. Majumdar ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2007 |
| Descrizione fisica | xxiv, 44, 21 : digital, PDF file |
| Altri autori (Persone) | MajumdarS (Saurindranath) |
| Soggetto topico | Steam-boilers - Failures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697846703321 |
| Washington, DC : , : Division of Fuel, Engineering, and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2007 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Steam generator tube integrity issues [[electronic resource] ] : pressurization rate effects, failure maps, leak rate correlation models, and leak rates in restricted areas / / prepared by S. Majumdar ... [and others]
| Steam generator tube integrity issues [[electronic resource] ] : pressurization rate effects, failure maps, leak rate correlation models, and leak rates in restricted areas / / prepared by S. Majumdar ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] |
| Descrizione fisica | 1 online resource (xxv, 73 pages) : illustrations (some color) |
| Altri autori (Persone) | MajumdarS (Saurindranath) |
| Soggetto topico |
Nuclear power plants - Piping - United States
Steam-pipes - Reliability |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Steam generator tube integrity issues |
| Record Nr. | UNINA-9910699037803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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