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Analysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests / / prepared by C. Queral, J. Mulas, C.G. de la Rua
| Analysis of the RELAP5/MOD3.2.2 beta critical flow models and assessment against critical flow data from the Marviken tests / / prepared by C. Queral, J. Mulas, C.G. de la Rua |
| Autore | Queral César |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2000 |
| Descrizione fisica | 1 online resource (xx, 74 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Nuclear reactors - Cooling - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706149303321 |
Queral César
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code : application to a PWR NPP model / / prepared by César Queral [and four others]
| Simulation of LSTF upper head break (OECD/NEA ROSA test 6.1) with TRACE code : application to a PWR NPP model / / prepared by César Queral [and four others] |
| Autore | Queral César |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (105 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Computer programs Nuclear power plants - Accidents - Management Pressurized water reactors - Accidents - Management |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Simulation of LSTF upper head break |
| Record Nr. | UNINA-9910705202603321 |
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Queral César
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Simulation of PKL loss of RHRS experiement F2..2 run 2 with RELAP5 and TRACE codes [[electronic resource] ] : application to a PWR NPP model / / prepared by César Queral, Antonio Expósito, and Alberto Concejal
| Simulation of PKL loss of RHRS experiement F2..2 run 2 with RELAP5 and TRACE codes [[electronic resource] ] : application to a PWR NPP model / / prepared by César Queral, Antonio Expósito, and Alberto Concejal |
| Autore | Queral César |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2011] |
| Descrizione fisica | 1 online resource (52 unnumbered pages) : illustrations |
| Altri autori (Persone) |
ExpósitoAntonio
ConcejalAlberto |
| 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 | Simulation of PKL loss of RHRS experiement F2..2 run 2 with RELAP5 and TRACE codes |
| Record Nr. | UNINA-9910701124103321 |
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Queral César
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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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Simulation of PKL loss of RHRS experiment E3.1 with RELAP5 and TRACE codes : application to a PWR NPP model / / prepared by César Queral [and three others]
| Simulation of PKL loss of RHRS experiment E3.1 with RELAP5 and TRACE codes : application to a PWR NPP model / / prepared by César Queral [and three others] |
| Autore | Queral César |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 2011 |
| Descrizione fisica | 1 online resource (various pagings) : 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 | Simulation of PKL loss of RHRS experiment E3.1 with RELAP5 and TRACE codes |
| Record Nr. | UNINA-9910707973003321 |
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Queral César
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , September 2011 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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