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Assessment of TRACE 5.0 against ROSA test 3-2, high power natural circulation [[electronic resource] /] / prepared by S. Gallardo ... [and others]
| Assessment of TRACE 5.0 against ROSA test 3-2, high power natural circulation [[electronic resource] /] / prepared by S. Gallardo ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (65 unnumbered pages) : color illustrations |
| Altri autori (Persone) | GallardoS |
| 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-9910701787003321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of TRACE 5.0 against ROSA test 6-2, vessel lower plenum SBLOCA [[electronic resource] /] / prepared by S. Gallardo, V. Abella, G. Verdú
| Assessment of TRACE 5.0 against ROSA test 6-2, vessel lower plenum SBLOCA [[electronic resource] /] / prepared by S. Gallardo, V. Abella, G. Verdú |
| Autore | Gallardo S |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (66 unnumbered pages) : color illustrations |
| Altri autori (Persone) |
AbellaV
VerdúG |
| 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-9910700590603321 |
Gallardo S
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| 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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An assessment of TRACE V5 RC1 code against UPTF counter current flow tests [[electronic resource] /] / prepared by S. Hillberg
| An assessment of TRACE V5 RC1 code against UPTF counter current flow tests [[electronic resource] /] / prepared by S. Hillberg |
| Autore | Hillberg S |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (59 unnumbered 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 |
| Altri titoli varianti | Assessment of TRACE/RELAP Advanced Computational Engine V5 RC1 code against Upper Plenum Test Facility counter current flow tests |
| Record Nr. | UNINA-9910700379103321 |
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Hillberg S
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of two-phase critical flow models performance in RELAPS and TRACE against Marviken critical flow tests [[electronic resource] /] / prepared by Lukasz Sokolowski and Tomasz Kozlowski
| Assessment of two-phase critical flow models performance in RELAPS and TRACE against Marviken critical flow tests [[electronic resource] /] / prepared by Lukasz Sokolowski and Tomasz Kozlowski |
| Autore | Sokolowski Lukasz |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2012] |
| Descrizione fisica | 1 online resource (85 unnumbered pages) : color illustrations |
| Altri autori (Persone) | KozłowskiTomasz |
| 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-9910701788003321 |
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Sokolowski Lukasz
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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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BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA / / prepared by Chunkuan Shih [and five others]
| BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , September 2015 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear reactor accidents - Analysis
Pressurized water reactors - Loss of coolant - Computer simulation Nuclear power plants - Licenses Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Best Estimate Plus Uncertainty analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA |
| Record Nr. | UNINA-9910704055603321 |
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Shih Chunkuan
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , September 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Coupled RELAP/PARCS full plant model [[electronic resource] ] : assessment of a cooling transient in Trillo Nuclear Power Plant / / prepared by J.C. Martinez-Murillo ... [and others]
| Coupled RELAP/PARCS full plant model [[electronic resource] ] : assessment of a cooling transient in Trillo Nuclear Power Plant / / prepared by J.C. Martinez-Murillo ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (44 unnumbered pages) : color illustrations |
| Altri autori (Persone) | Marinez-MurilloJ. C |
| 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 Nuclear power plants - Spain |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Coupled RELAP/PARCS full plant model |
| Record Nr. | UNINA-9910700975803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Development of a Vandellos II NPP model using the TRACE code [[electronic resource] ] : application to an actual transient of main coolant pumps trip and start-up / / prepared by O. Lozano ... [and others]
| Development of a Vandellos II NPP model using the TRACE code [[electronic resource] ] : application to an actual transient of main coolant pumps trip and start-up / / prepared by O. Lozano ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 online resource (45 pages) : color illustrations |
| Altri autori (Persone) | LozanoO |
| 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 |
| Altri titoli varianti | Development of a Vandellos II NPP model using the TRACE code |
| Record Nr. | UNINA-9910700378403321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments : model changes and options / / prepared by G. Th. Analytis
| Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments : model changes and options / / prepared by G. Th. Analytis |
| Autore | Analytis G. Th (Gerassimos Th.) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1998 |
| Descrizione fisica | 1 online resource (v, 39 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Nuclear reactor accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Developmental assessment of RELAP5/MOD3.1 with separate-effect and integral test experiments |
| Record Nr. | UNINA-9910705828803321 |
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Analytis G. Th (Gerassimos Th.)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 1998 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / / Prepared by: Sebastian Gurgacz [and five others]
| EPR medium break LOCA benchmarking exercise using RELAP5 and CATHARE / / Prepared by: Sebastian Gurgacz [and five others] |
| Autore | Gurgacz Sebastian |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 |
| Descrizione fisica | 1 online resource (57 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant - Computer simulation
Light water reactors - Accidents - Computer simulation Nuclear power plants - Design and construction - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | European Pressurized Reactor medium break Loss Of Coolant Accident benchmarking exercise using Reactor Excursion and Leak Analysis Program5 and Code for Analysis of Thermal Hydraulics during an Accident of Reactor and safety Evaluation |
| Record Nr. | UNINA-9910704262503321 |
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Gurgacz Sebastian
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Evaluation of semi-scale small break experiment
| Evaluation of semi-scale small break experiment |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715468003321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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