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LBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 / / prepared by J.I. Sánchez, C.A. Lage, T. Núñuz
| LBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 / / prepared by J.I. Sánchez, C.A. Lage, T. Núñuz |
| Autore | Sánchez J. I. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 |
| Descrizione fisica | 1 online resource (ix, 61 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706146303321 |
Sánchez J. I.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Numerics and implementation of the UK horizontal stratification entrainment off-take model into RELAP5/MOD3 / / prepared by W. M. Bryce
| Numerics and implementation of the UK horizontal stratification entrainment off-take model into RELAP5/MOD3 / / prepared by W. M. Bryce |
| Autore | Bryce W. M. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (viii, 34 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707739503321 |
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Bryce W. M.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Performing uncertainty analysis of IIST facility SBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang ... [and three others]
| Performing uncertainty analysis of IIST facility SBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang ... [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Performing uncertainty analysis of Institute of Nuclear Energy Research Integral System Test facility SBLOCA by TRACE and DAKOTA |
| Record Nr. | UNINA-9910704990103321 |
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Wang Jong-Rong
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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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Post-test calculation of the ROSA/LSTF test 3-1 using RELAP5/Mod3.3 [[electronic resource] /] / prepared by V. Martinez, F. Reventós, C. Pretel
| Post-test calculation of the ROSA/LSTF test 3-1 using RELAP5/Mod3.3 [[electronic resource] /] / prepared by V. Martinez, F. Reventós, C. Pretel |
| Autore | Martinez V |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (49 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
ReventósF
PretelC |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701504803321 |
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Martinez V
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Post-test calculation of the ROSA/LSTF test 3-2 using RELAP5/Mod3.3 [[electronic resource] /] / prepared by V. Martinez, F. Reventós, C. Pretel
| Post-test calculation of the ROSA/LSTF test 3-2 using RELAP5/Mod3.3 [[electronic resource] /] / prepared by V. Martinez, F. Reventós, C. Pretel |
| Autore | Martinez V |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (45 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
ReventósF
PretelC |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910701504703321 |
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Martinez V
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
| Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
Nuclear power plants - Computer programs - Testing Pressurized water reactors - Loss of coolant - Computer simulation Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703560503321 |
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Freixa J.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Qualification of the three-dimensional thermal hydraulic model of TRACE using plant data [[electronic resource] /] / prepared by V. Sanchez-Espinoza
| Qualification of the three-dimensional thermal hydraulic model of TRACE using plant data [[electronic resource] /] / prepared by V. Sanchez-Espinoza |
| Autore | Sánchez-Espinoza Victor Hugo |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (xiii, 27 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910700378903321 |
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Sánchez-Espinoza Victor Hugo
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RBHT reflood heat transfer experiments data and analysis [[electronic resource] /] / prepared by L.E. Hochreiter ... [and others]
| RBHT reflood heat transfer experiments data and analysis [[electronic resource] /] / prepared by L.E. Hochreiter ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, , [2012] |
| Descrizione fisica | 1 online resource (599 unnumbered pages) : color illustrations |
| Altri autori (Persone) | HochreiterL. E |
| Soggetto topico |
Nuclear fuel rods - Experiments
Heat-transfer media - Experiments Pressurized water reactors - Loss of coolant - Computer simulation Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Rod Bundle Heat Transfer reflood heat transfer experiments data and analysis |
| Record Nr. | UNINA-9910702036803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Rgulatory Research, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5 analysis of mitigation strategy for extended blackout power condition in PWR / / prepared by Andrej Prošek, Andrija Volkanovski
| RELAP5 analysis of mitigation strategy for extended blackout power condition in PWR / / prepared by Andrej Prošek, Andrija Volkanovski |
| Autore | Prošek Andrej <1962-> |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2016 |
| Descrizione fisica | 1 online resource (xv, 23 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707285003321 |
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Prošek Andrej <1962->
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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RELAP5 assessment using LSTF test data SB-CL-18 / / prepared by S. Lee, B.D. Chung, H.J. Kim
| RELAP5 assessment using LSTF test data SB-CL-18 / / prepared by S. Lee, B.D. Chung, H.J. Kim |
| Autore | Lee Sukho |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1993 |
| Descrizione fisica | 1 online resource (xii, 206 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707740103321 |
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Lee Sukho
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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