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Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code / / prepared by J. Blanco [and three others]
| Analysis of the LOBI experiment test BT-56 using the RELAP5/MOD3.2 code / / prepared by J. Blanco [and three others] |
| Autore | Blanco J. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 2000 |
| Descrizione fisica | 1 online resource (xiii, 55 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Computer simulation
Pressurized water reactors - Accidents - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706151303321 |
Blanco J.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / / prepared by S. Cho [and three others]
| Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / / prepared by S. Cho [and three others] |
| Autore | Cho S. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (114 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear fuel rods - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708490003321 |
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Cho S.
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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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Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera nuclear station / / prepared by R. Arroyo, L. Rebollo
| Assessment of RELAP5/MOD2 against a pressurizer spray valve inadverted fully opening transient and recovery by natural circulation in Jose Cabrera nuclear station / / prepared by R. Arroyo, L. Rebollo |
| Autore | Arroyo R. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (xi, 44, 60 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear reactor accidents - Spain - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707851403321 |
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Arroyo R.
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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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Assessment of TRACE 5.0 against ROSA-2 test 3 countertest to PKL / / prepared by S. Gallardo [and three others]
| Assessment of TRACE 5.0 against ROSA-2 test 3 countertest to PKL / / prepared by S. Gallardo [and three others] |
| Autore | Gallardo S. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , March 2019 |
| Descrizione fisica | 1 online resource (xvii, 37 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Computer programs Nuclear power plants - Accidents Pressurized water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910712080003321 |
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Gallardo S.
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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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The development and verification of TRACE model for IIST experiments [[electronic resource] /] / prepared by, Jong-Rong Wang ... [and others]
| The development and verification of TRACE model for IIST experiments [[electronic resource] /] / prepared by, Jong-Rong Wang ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (65 unnumbered pages) : color illustrations |
| Altri autori (Persone) | WangJong-Rong |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - 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-9910700312403321 |
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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IBLOCA analysis for Vandellós-NPP using RELAP5/MOD3.3 sensitivity calculations to EOP actions / / prepared by M. Pérez-Ferrgut [and three others]
| IBLOCA analysis for Vandellós-NPP using RELAP5/MOD3.3 sensitivity calculations to EOP actions / / prepared by M. Pérez-Ferrgut [and three others] |
| Autore | Pérez-Ferrgut M. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , February 2019 |
| Descrizione fisica | 1 online resource (xvii, 30 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Accidents - Computer simulation
Nuclear power plants - Computer programs Nuclear power plants - Accidents - Spain |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Intermediate Break Loss Of Coolant Accident analysis for Vandellós Nuclear Power Plant using RELAP5/MOD3.3 sensitivity calculations to Emergency Operaton Procedure actions |
| Record Nr. | UNINA-9910711907103321 |
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Pérez-Ferrgut M.
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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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Implementation of the control rod movement option by means of control variables in RELAP5/PARCS v2.7 coupled code / / prepared by R. Miro [and six others]
| Implementation of the control rod movement option by means of control variables in RELAP5/PARCS v2.7 coupled code / / prepared by R. Miro [and six others] |
| Autore | Miró R. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (105 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear accidents - Control - Computer programs
Nuclear reactors - Safety measures - Computer simulation Pressurized water reactors - Accidents - Computer simulation Nuclear power plants - Accidents - Management |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702586803321 |
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Miró R.
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| Washington, DC : , : United States Nuclear Regulatory Commission, , 2014 | ||
| 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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Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code : application to a PWR NPP model / / prepared by Juan Gonzalez-Cadelo [and four others]
| Simulation of LSTF hot leg break (OECD/NEA ROSA-2 test 1) with TRACE code : application to a PWR NPP model / / prepared by Juan Gonzalez-Cadelo [and four others] |
| Autore | Gonzalez-Cadelo Juan |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (81 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 hot leg break |
| Record Nr. | UNINA-9910705318303321 |
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Gonzalez-Cadelo Juan
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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 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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