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Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà
| Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà |
| Autore | Muñoz-Cobo J. L. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (37 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis with TRAC/RELAP Advanced Computational Engine code of PKL-III test F 1.2 |
| Record Nr. | UNINA-9910704414903321 |
Muñoz-Cobo J. L.
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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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Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3 / / prepared by O.A. Berar, A. Prosek
| Assessment against ACHILLES reflood experiment with TRACE V5.0 Patch3 / / prepared by O.A. Berar, A. Prosek |
| Autore | Berar Ovidiu-Adrian |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (xiii, 25 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
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-9910705253003321 |
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Berar Ovidiu-Adrian
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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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Assessment of RELAP5/MOD3.2.2 gamma with the LOFT L9-3 experiment simulating an anticipated transient without scram / / prepared by J.K. Suh, Y.S. Bang, H.J. Kim
| Assessment of RELAP5/MOD3.2.2 gamma with the LOFT L9-3 experiment simulating an anticipated transient without scram / / prepared by J.K. Suh, Y.S. Bang, H.J. Kim |
| Autore | Suh J. K (Jeung Keun) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2001 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Accidents - Computer simulation
LOFT (Nuclear reactor safety test facility) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706146703321 |
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Suh J. K (Jeung Keun)
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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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Assessment of RELAP5/MOD3.2.2y against flooding database in horizontal-to-inclined pipes / / prepared by H.T. Kim [and four others]
| Assessment of RELAP5/MOD3.2.2y against flooding database in horizontal-to-inclined pipes / / prepared by H.T. Kim [and four others] |
| Autore | Kim H. T. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2001 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Thermodynamics - Computer simulation
Nuclear power plants - Accidents - Computer simulation Nuclear power plants - Thermodynamics - Computer simulation Nuclear power plants - Risk assessment - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment of RELAP5/MOD3.2.2[gamma] against flooding database in horizontal-to-inclined pipes |
| Record Nr. | UNINA-9910706113903321 |
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Kim H. T.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of TRACE 5.0 against ROSA test 3-1, cold leg SBLOCA [[electronic resource] /] / prepared by S. Gallardo ... [and others]
| Assessment of TRACE 5.0 against ROSA test 3-1, cold leg SBLOCA [[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-9910701786803321 |
| 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 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 |
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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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