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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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Behaviour of spent power reactor fuel during storage : extracts from the Final Reports of Coordinated Research Projects on Behaviour of Spent Fuel Assemblies (BEFAST I-III) and Spent Fuel Performance Assessment and Research (SPAR I-III) - 1981-2014 / / International Atomic Energy Agency
| Behaviour of spent power reactor fuel during storage : extracts from the Final Reports of Coordinated Research Projects on Behaviour of Spent Fuel Assemblies (BEFAST I-III) and Spent Fuel Performance Assessment and Research (SPAR I-III) - 1981-2014 / / International Atomic Energy Agency |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2019] |
| Descrizione fisica | 1 online resource (113 pages) : illustrations |
| Disciplina | 621.4838 |
| Collana | IAEA-TECDOC |
| Soggetto topico | Spent reactor fuels - Storage |
| ISBN | 92-0-156919-X |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910793877303321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2019] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Behaviour of spent power reactor fuel during storage : extracts from the Final Reports of Coordinated Research Projects on Behaviour of Spent Fuel Assemblies (BEFAST I-III) and Spent Fuel Performance Assessment and Research (SPAR I-III) - 1981-2014 / / International Atomic Energy Agency
| Behaviour of spent power reactor fuel during storage : extracts from the Final Reports of Coordinated Research Projects on Behaviour of Spent Fuel Assemblies (BEFAST I-III) and Spent Fuel Performance Assessment and Research (SPAR I-III) - 1981-2014 / / International Atomic Energy Agency |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2019] |
| Descrizione fisica | 1 online resource (113 pages) : illustrations |
| Disciplina | 621.4838 |
| Collana | IAEA-TECDOC |
| Soggetto topico | Spent reactor fuels - Storage |
| ISBN | 92-0-156919-X |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910812498203321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2019] | ||
| 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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Boraflex degradation in spent fuel pool storage racks [[electronic resource]]
| Boraflex degradation in spent fuel pool storage racks [[electronic resource]] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1996] |
| Descrizione fisica | 1 online resource |
| Collana | NRC generic letter |
| Soggetto topico |
Neutron absorbers - Deterioration
Spent reactor fuels - Storage |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699544903321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1996] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Boraflex degradation surveillance programs and corrective actions in the spent fuel pool
| Boraflex degradation surveillance programs and corrective actions in the spent fuel pool |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation : , : Office of New Reactors : , : Office of Federal and State Materials and Environmental Management Programs, , 2012 |
| Descrizione fisica | 1 online resource (4 pages) |
| Collana | NRC information notice |
| Soggetto topico |
Spent reactor fuels - Storage
Neutron absorbers - Deterioration |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910716665603321 |
Degradation of Boraflex neutron absorber in spent fuel storage racks [[electronic resource]]
| Degradation of Boraflex neutron absorber in spent fuel storage racks [[electronic resource]] |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1995] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Spent reactor fuels - Storage
Neutron absorbers - Defects |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910700276303321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1995] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Degradation of neutron-absorbing materials in the spent fuel pool [[electronic resource]]
| Degradation of neutron-absorbing materials in the spent fuel pool [[electronic resource]] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [2009] |
| Descrizione fisica | 1 online resource (4 pages) |
| Collana | NRC information notice |
| Soggetto topico |
Neutron absorbers - Deterioration
Spent reactor fuels - Storage |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699531203321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [2009] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Deradation of boraflex neutron absorber coupons
| Deradation of boraflex neutron absorber coupons |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1993] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Spent reactor fuels - Storage
Neutron absorbers - Defects |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910703426603321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1993] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Emplacement of support pads for spent fuel dry storage installations at reactor sites [[electronic resource]]
| Emplacement of support pads for spent fuel dry storage installations at reactor sites [[electronic resource]] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , [1995] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Spent reactor fuels - Storage
Nuclear facilities - United States |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910700137803321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, , [1995] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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