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Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2 / / prepared by L. Batet, F. Reventós
| Analysis of PANDA experiments P3 and P6 using RELAP5/MOD3.2 / / prepared by L. Batet, F. Reventós |
| Autore | Batet L. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 |
| Descrizione fisica | 1 online resource (xi, 16 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Water cooled reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706146203321 |
Batet L.
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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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Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós
| Core exit temperature response during an SBLOCA event in the Ascó NPP / / prepared by J. Freixa, V. Martínez-Quiroga, F. Reventós |
| Autore | Freixa J. |
| Pubbl/distr/stampa | Washington., DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , December 2018 |
| Descrizione fisica | 1 online resource (xvii, 30 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear reactors - Cores |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Core exit temperature response during an Small Break LOss of Coolant Acicident event in the Ascó Nuclear Power Plant |
| Record Nr. | UNINA-9910711961103321 |
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Freixa J.
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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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Post-test calculation of the PKL-2 test G7.1 using RELAP5/MOD3.3 / / prepared by V. Martinez-Quiroga, F. Reventos, C. Pretel
| Post-test calculation of the PKL-2 test G7.1 using RELAP5/MOD3.3 / / prepared by V. Martinez-Quiroga, F. Reventos, C. Pretel |
| Autore | Martínez-Quiroga Victor |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , February 2019 |
| Descrizione fisica | 1 online resource (xv, 17 pages) : illustrations (chiefly color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711905303321 |
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Martínez-Quiroga Victor
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , February 2019 | ||
| 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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Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2 [[electronic resource] /] / prepared by R. Pericas, L. Batet, and F. Reventós
| Sensitivity analyses of a hypothetical 6 inch break, LOCA in Ascó NPP using RELAP/MOD3.2 [[electronic resource] /] / prepared by R. Pericas, L. Batet, and F. Reventós |
| Autore | Pericas R |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Systems Analysis, , 2010 |
| Descrizione fisica | 1 online resource (50 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
BatetL
ReventósF |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear power plants - Accidents Nuclear power plants - Spain |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699966103321 |
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Pericas R
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Systems Analysis, , 2010 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario / / prepared by C. Pretel, F. Reventós
| Study of unusual occurrence of a partial core uncovery in an SBLOCA scenario / / prepared by C. Pretel, F. Reventós |
| Autore | Pretel C. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 2000 |
| Descrizione fisica | 1 online resource (vi, 30 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-9910705835803321 |
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Pretel C.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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