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Assessment of channel coolant voiding in RD-14M test facility using TRACE / / prepared by Andrew Oussoren, Aleksandar Delja
| Assessment of channel coolant voiding in RD-14M test facility using TRACE / / prepared by Andrew Oussoren, Aleksandar Delja |
| Autore | Oussoren Andrew |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (65 unnumbered pages) : color illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
CANDU reactors - Analysis
Nuclear reactors - Cooling Nuclear reactor accidents - Analysis |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702693403321 |
Oussoren Andrew
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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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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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Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others]
| Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] |
| Descrizione fisica | 1 online resource (61 pages) : illustrations |
| Altri autori (Persone) |
ChoYŏng-jin
CalvoA |
| Collana | International agreement report |
| Soggetto topico |
CANDU reactors - Accidents - Analysis
Nuclear reactor accidents - Analysis Nuclear reactors - Fluid dynamics - Models |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699323103321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others]
| Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods
Nuclear reactor accidents - Analysis Pressurized water reactors - Loss of coolant - Analysis Nuclear power plants - Taiwan |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707412703321 |
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Shih Chunkuan
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others]
| Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Nuclear reactor accidents - Analysis
Nuclear reactor accidents - Computer simulation Pressurized water reactors - Loss of coolant - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702555803321 |
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Wang Jong-Rong
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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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