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Assessment of RELAP5/MOD2 cycle 36.04 using LOFT intermediate break experiment L5-1 / / prepared by E.J. Lee, B.D. Cung, H.J. Kim
| Assessment of RELAP5/MOD2 cycle 36.04 using LOFT intermediate break experiment L5-1 / / prepared by E.J. Lee, B.D. Cung, H.J. Kim |
| Autore | Lee E. J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1992 |
| Descrizione fisica | 1 online resource (ix, 46, 86 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707780503321 |
Lee E. J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1992 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of RELAP5/MOD2, cycle 36.04 using LOFT large break experiment L2-5 / / prepared by Young Seok Bang, Sang Yong Lee, Hho-Jung Kim
| Assessment of RELAP5/MOD2, cycle 36.04 using LOFT large break experiment L2-5 / / prepared by Young Seok Bang, Sang Yong Lee, Hho-Jung Kim |
| Autore | Bang Seok Young |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 |
| Descrizione fisica | 1 online resource (xi, 169 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707626703321 |
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Bang Seok Young
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data / / prepared by F. Odar
| Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data / / prepared by F. Odar |
| Autore | Odar Fuat |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2001 |
| Descrizione fisica | 1 online resource (xi, 82 pages) : illustrations |
| Soggetto topico |
Pressurized water reactors - Thermodynamics - Computer programs
Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment of the TRAC M codes using Flecht-Seaset reflood and steam cooling data |
| Record Nr. | UNINA-9910708659503321 |
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Odar Fuat
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| Washington, DC : , : Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of TRACE V5.0.Patch 4 code against PWR PACTEL loop seal clearing experiment / / prepared by: Otso-Pekka Kauppinen
| Assessment of TRACE V5.0.Patch 4 code against PWR PACTEL loop seal clearing experiment / / prepared by: Otso-Pekka Kauppinen |
| Autore | Kauppinen Otso-Pekka |
| Pubbl/distr/stampa | Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 |
| Descrizione fisica | 1 online resource (xiii, 23 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer programs
Thermal hydraulics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment of TRACE V5.0.Patch 4 code against Pressurized Water Reactor PArallel Channel TEst Loop loop seal clearing experiment |
| Record Nr. | UNINA-9910711940303321 |
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Kauppinen Otso-Pekka
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| Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests / / prepared by E.J. Stubbe, L. Vanhoenacker
| Assessment study of RELAP5/MOD2 cycle 36.04 based on pressurizer safety and relief valve tests / / prepared by E.J. Stubbe, L. Vanhoenacker |
| Autore | Stubbe E. J (Elie J.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1990 |
| Descrizione fisica | 1 online resource (37 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Safety measures - Simulation methods
Relief valves - Testing Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707626103321 |
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Stubbe E. J (Elie J.)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment study of RELAP5/MOD2, CYCLE 36.04 based on spray start-up test for DOEL-4 / / prepared by P. Moeyaert, E. Stubbe
| Assessment study of RELAP5/MOD2, CYCLE 36.04 based on spray start-up test for DOEL-4 / / prepared by P. Moeyaert, E. Stubbe |
| Autore | Moeyaert P. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1989 |
| Descrizione fisica | 1 online resource (428 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Safety measures - Simulation methods
Pressurized water reactors - Control Relief valves - Testing Pressurized water reactors - Loss of coolant - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707646003321 |
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Moeyaert P.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 1989 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Investigation of the loop seal clearing phenomena for the ATLAS DVI line and cold leg SBLOCA tests using MARS-KS and RELAP5/MOD3.3 / / prepared by Minjeong Hwang [and three others]
| Investigation of the loop seal clearing phenomena for the ATLAS DVI line and cold leg SBLOCA tests using MARS-KS and RELAP5/MOD3.3 / / prepared by Minjeong Hwang [and three others] |
| Autore | Hwang Minjeong |
| Pubbl/distr/stampa | Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 |
| Descrizione fisica | 1 online resource (xvolumes 49 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer programs
Thermal hydraulics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Investigation of the loop seal clearing phenomena for the Advanced Thermal-hydraulic test Loop for Accident Simulation Direct Vessel Injection line and cold leg Small Break Loss Of Coolant Accident tests using Multi-dimensional Advanced Reactor Safety program-Korea Standard and Reactor Excursion and Leak Analysis Program 5/MOD3.3 |
| Record Nr. | UNINA-9910712081803321 |
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Hwang Minjeong
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| Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 / / prepared by E.J. Allen
| TRAC-PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 / / prepared by E.J. Allen |
| Autore | Allen E. J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Loss of coolant - Computer programs Transients (Dynamics) - Simulation methods |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC PF1 MOD1 post test calculations of the OECD LOFT experiment LP-SB-1 |
| Record Nr. | UNINA-9910707644403321 |
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Allen E. J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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TRAC-PF1/MOD1 post-test calculations of the OECD loft experiment LP-SB-2 / / prepared by F. Pelayo
| TRAC-PF1/MOD1 post-test calculations of the OECD loft experiment LP-SB-2 / / prepared by F. Pelayo |
| Autore | Pelayo F. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 1990 |
| Descrizione fisica | 1 online resource (x, 151 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Loss of coolant - Computer programs Hydraulic transients - Simulation methods |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC PF1/MOD1 post test calculations of the OECD loft experiment LP-SB-2 |
| Record Nr. | UNINA-9910707645903321 |
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Pelayo F.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 / / prepared by E. J. Allen, A. P. Neill
| TRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 / / prepared by E. J. Allen, A. P. Neill |
| Autore | Allen E. J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 |
| Descrizione fisica | 1 online resource (112 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
LOFT (Nuclear reactor safety test facility) - Experiments
Pressurized water reactors - Loss of coolant - Computer programs Hydraulic transients - Simulation methods |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC PF1/MOD1 post test calculations of the OECD LOFT experiment LP-SB-3 |
| Record Nr. | UNINA-9910707645003321 |
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Allen E. J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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