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 | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar
| Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar |
| Autore | Oussoren Andrew |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 |
| Descrizione fisica | 1 online resource (xv, 29 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear power plants - Piping - Cracking |
| Soggetto genere / forma | Online resources. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706176303321 |
Oussoren Andrew
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 | ||
| Lo trovi qui: Univ. Federico II | ||
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