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ATWS
| ATWS |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , [1979] |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear reactors - Safety measures
Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | ATWS |
| Record Nr. | UNINA-9910715456303321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , [1979] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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ATWS-enclosing letter to GE, with NUREG-0460, vol. 3
| ATWS-enclosing letter to GE, with NUREG-0460, vol. 3 |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear reactors - Safety measures
Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Anticipated transients without scram for light water reactors |
| Record Nr. | UNINA-9910715471903321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit / / prepared by William (B.J.) Marshall [and three others]
| Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit / / prepared by William (B.J.) Marshall [and three others] |
| Autore | Marshall William (William B. J.) |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , August 2016 |
| Descrizione fisica | 1 online resource (xi, 99, A4 pages) : color illustrations |
| Soggetto topico |
Boiling water reactors
Spent reactor fuels - Storage Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707689303321 |
Marshall William (William B. J.)
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , August 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / / prepared by D.E. Mueller [and three others]
| Bias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks / / prepared by D.E. Mueller [and three others] |
| Autore | Mueller D. E. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , September 2015 |
| Descrizione fisica | 1 online resource (73 unnumbered pages) : color illustrations |
| Soggetto topico |
Fission products - Handling
Monte Carlo method Actinide elements Fuel burnup (Nuclear engineering) Spent reactor fuels - Storage Spent reactor fuels - Transportation Pressurized water reactors |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698624303321 |
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Mueller D. E.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , September 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Criticality analysis of assembly misload in a PWR burnup credit cask [[electronic resource] /] / prepared by J.C. Wagner
| Criticality analysis of assembly misload in a PWR burnup credit cask [[electronic resource] /] / prepared by J.C. Wagner |
| Autore | Wagner J. C |
| Pubbl/distr/stampa | [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] |
| Descrizione fisica | xiv, 25 pages : digital, PDF file |
| Soggetto topico | Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910696839103321 |
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Wagner J. C
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| [Washington, D.C.] : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2008] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Dry storage and transportation of high-burnup spent nuclear fuel : draft report for comment / / prepared by T. Ahn [and nine others]
| Dry storage and transportation of high-burnup spent nuclear fuel : draft report for comment / / prepared by T. Ahn [and nine others] |
| Autore | Ahn T. M. |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , July 2018 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Fuel burnup (Nuclear engineering)
Spent reactor fuels - Transportation Nuclear fuels |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Dry storage and transportation of high-burnup spent nuclear fuel |
| Record Nr. | UNINA-9910711458003321 |
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Ahn T. M.
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , July 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions / / prepared by L. Yegorova [and eight others]
| Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel (VVER type) under reactivity-initiated accident conditions / / prepared by L. Yegorova [and eight others] |
| Autore | Yegorova L. A (Larisa Alexandrovna) |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 |
| Descrizione fisica | 1 online resource (2 volumes) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Fuel burnup (Nuclear engineering)
Nuclear fuels Nuclear reactors - Reactivity |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | vol. 1. Program approach and analysis of results -- vol. 2. Test conditions and results. |
| Altri titoli varianti | Experimental study of narrow pulse effects on the behavior of high burnup fuel rods with Zr-1%Nb cladding and UO₂ fuel |
| Record Nr. | UNINA-9910702327503321 |
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Yegorova L. A (Larisa Alexandrovna)
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2006 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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High burnup MAPLHGR limits
| High burnup MAPLHGR limits |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1982 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear fuels
Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | High burnup maximum average planar linear heat generation rate limits |
| Record Nr. | UNINA-9910715901903321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1982 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Impact of operating parameters on extended BWR burnup credit / / Brian J. Ade [and four others]
| Impact of operating parameters on extended BWR burnup credit / / Brian J. Ade [and four others] |
| Autore | Ade Brian |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , January 2018 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Boiling water reactors
Spent reactor fuels - Storage Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Impact of operating parameters on extended boiling water reactors burnup credit |
| Record Nr. | UNINA-9910706919603321 |
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Ade Brian
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| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , January 2018 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Mechanical fatigue testing of high-burnup fuel for transportation applications / / prepared by Jy-An Wang and Hong Wang
| Mechanical fatigue testing of high-burnup fuel for transportation applications / / prepared by Jy-An Wang and Hong Wang |
| Autore | Wang Jy-An |
| Edizione | [Rev. 1.] |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2017 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Fuel burnup (Nuclear engineering)
Spent reactor fuels - Transportation Fracture mechanics Nuclear fuels |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706511403321 |
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Wang Jy-An
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2017 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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