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Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding / / prepared by A. Shestopalov, K. Lioutov, L. Yegorova
| Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding / / prepared by A. Shestopalov, K. Lioutov, L. Yegorova |
| Autore | Shestopalov A. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , April 2003 |
| Descrizione fisica | 1 online resource (xiii, 51 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel claddings
Niobium-zirconium alloys Nuclear fuel rods - Safety measures Fuel burnup (Nuclear engineering) - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb |
| Record Nr. | UNINA-9910707861503321 |
Shestopalov A.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , April 2003 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Margins for uncertainty in the predicted spent fuel isotopic inventories for BWR burnup credit / / prepared by: I. Guald, U. Mertyurek ; Mourad Aissa, NRC project manager
| Margins for uncertainty in the predicted spent fuel isotopic inventories for BWR burnup credit / / prepared by: I. Guald, U. Mertyurek ; Mourad Aissa, NRC project manager |
| Autore | Gauld I. C. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 |
| Descrizione fisica | 1 online resource (various pagings) : color illustrations |
| Soggetto topico |
Uncertainty - Mathematical models
Fuel burnup (Nuclear engineering) - Safety measures Spent reactor fuels - Safety measures Boiling water reactors - Safety measures Nuclides |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711991403321 |
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Gauld I. C.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Validation of ke̳f̳f̳ calculations for extended BWR burnup credit / / prepared by: W. J. Marshall, J. B. Clarity, S. M. Bowman ; Mourad Aissa, NRC project manager
| Validation of ke̳f̳f̳ calculations for extended BWR burnup credit / / prepared by: W. J. Marshall, J. B. Clarity, S. M. Bowman ; Mourad Aissa, NRC project manager |
| Autore | Marshall William (William B. J.) |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 |
| Descrizione fisica | 1 online resource (approximately 117 pages) : color illustrations |
| Soggetto topico |
Boiling water reactors - United States - Safety measures
Fuel burnup (Nuclear engineering) - Safety measures Actinide elements Boiling water reactors - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711844603321 |
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Marshall William (William B. J.)
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , December 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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