Analysis of semiscale test S-LH-1 using RELAP5/MOD2 / / prepared by P.C. Hall, D.R. Bull |
Autore | Hall P. C (Peter C.) |
Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 |
Descrizione fisica | 1 online resource (v, 32 pages) : illustrations |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis of semiscale test S LH 1 using RELAP5/MOD2 |
Record Nr. | UNINA-9910707780003321 |
Hall P. C (Peter C.) | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1992 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
Autore | Belaïd S. |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
Descrizione fisica | 1 online resource (xiii, 29 pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement Nuclear fuel claddings - Effect of temperature on - Measurement Nuclear power plants - Safety measures - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE |
Record Nr. | UNINA-9910704812803321 |
Belaïd S. | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Characterization and head-loss testing of latent debris from pressurized-water-reactor containment buildings [[electronic resource] /] / prepared by M. Ding ... [and others] |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2005 |
Descrizione fisica | xviii, 103 pages : digital, PDF file |
Altri autori (Persone) | DingMingzhou |
Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing Nuclear reactors - Containment - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Characterization and head loss testing of latent debris from pressurized-water-reactor containment buildings |
Record Nr. | UNINA-9910697330803321 |
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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RELAP/MOD3 analysis of BETHSY test 6.9c : loss of RHRS: SG manway open / / prepared by G.R. Kimber, M.A. George |
Autore | Kimber G. R. |
Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2000 |
Descrizione fisica | 1 online resource (vii, 49 pages) : illustrations |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | RELAP/MOD3 analysis of BETHSY test 6.9c |
Record Nr. | UNINA-9910706149203321 |
Kimber G. R. | ||
Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2000 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Screen penetration test report [[electronic resource] /] / prepared by A. Maji, K. Howe, and F. Carles |
Autore | Ma Jia |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2005 |
Descrizione fisica | xii, 34 pages : digital, PDF file |
Altri autori (Persone) |
HoweK
CarlesF |
Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing Pressurized water reactors - Loss of coolant |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910697316203321 |
Ma Jia | ||
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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