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Analysis of semiscale test S-LH-1 using RELAP5/MOD2 / / prepared by P.C. Hall, D.R. Bull
| 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.)
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| 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
| 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 |
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Belaïd S.
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| 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]
| 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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LOFT system and test description (5.5-ft nuclear core 1 loces) / / Douglas L. Reeder
| LOFT system and test description (5.5-ft nuclear core 1 loces) / / Douglas L. Reeder |
| Autore | Reeder Douglas L. |
| Edizione | [[Rev. 2].] |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission |
| Descrizione fisica | 1 online resource (ix, 481 pages) : illustrations |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility)
Pressurized water reactors - Testing Pressurized water reactors - Safety measures Nuclear reactors - United States - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | LOFT system and test description |
| Record Nr. | UNINA-9910707410103321 |
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Reeder Douglas L.
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| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Overpressurization test of a 1:4-scale prestressed concrete containment vessel model / / prepared by M.F. Hessheimer ... [and others]
| Overpressurization test of a 1:4-scale prestressed concrete containment vessel model / / prepared by M.F. Hessheimer ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Engineering Technology |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | HessheimerM. F (Michael F.) |
| Soggetto topico |
Pressurized water reactors - Testing
Pressure vessels - Testing Nuclear pressure vessels - Models Nuclear reactors - Containment - Materials - Testing Prestressed concrete construction - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Overpressurization test of a 1 |
| Record Nr. | UNINA-9910697358403321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Engineering Technology | ||
| 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
| 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 |
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Kimber G. R.
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| 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
| 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 |
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Ma Jia
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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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Steam Generator Tube Integrity Program/Steam Generator Group Project : final project summary report / / prepared by R.J. Kurtz [and six others]
| Steam Generator Tube Integrity Program/Steam Generator Group Project : final project summary report / / prepared by R.J. Kurtz [and six others] |
| Autore | Kurtz R. J. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1990 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations (some color) |
| Soggetto topico |
Steam-boilers - United States - Testing
Steam generating heavy water reactors - Testing Pressurized water reactors - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Steam Generator Tube Integrity Program/Steam Generator Group Project |
| Record Nr. | UNINA-9910706824003321 |
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Kurtz R. J.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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