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Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA / / prepared by V.A. Vinogradov, A.Y. Balykin
| Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA / / prepared by V.A. Vinogradov, A.Y. Balykin |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706114003321 |
Vinogradov V. A.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 / / prepared by V.A. Vinogradov, A.Y. Balykin
| Analysis of KS-1 experimental data on the behavior of the heated rod temperatures in the partially uncovered VVER core model using RELAP5/MOD3.2 / / prepared by V.A. Vinogradov, A.Y. Balykin |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 1999 |
| Descrizione fisica | 1 online resource (110 unnumbered pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel rods - Thermal properties - Computer simulation
Nuclear fuels - Analysis - Computer simulation Nuclear fuel elements - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707110003321 |
|
Vinogradov V. A.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 1999 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma / / prepared by V.A. Vinogradov, and A.Y. Balykin
| Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma / / prepared by V.A. Vinogradov, and A.Y. Balykin |
| Autore | Vinogradov V. A. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2002 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico | Pressurized water reactors - Loss of coolant - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706113603321 |
|
Vinogradov V. A.
|
||
| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , July 2002 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||