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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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Cladding rupture, swelling & coolant blockage as a result of a reactor accident
| Cladding rupture, swelling & coolant blockage as a result of a reactor accident |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear power plants - Accidents
Nuclear fuel claddings |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910715976203321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1979 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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ECCS calculations on fuel cladding
| ECCS calculations on fuel cladding |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , [1979] |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear fuel claddings
Emergency core cooling systems |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Emergency core cooling systems calculations on fuel cladding |
| Record Nr. | UNINA-9910715980803321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , [1979] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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NUREG-0630 "Cladding, swelling and rupture--models for LOCA analysis"
| NUREG-0630 "Cladding, swelling and rupture--models for LOCA analysis" |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Nuclear fuel claddings
Nuclear power plants - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | NUREG-0630 "Cladding, swelling and rupture--models for loss of coolant accident analysis" |
| Record Nr. | UNINA-9910715973903321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Predicted increase in fuel rod cladding oxidation [[electronic resource]]
| Predicted increase in fuel rod cladding oxidation [[electronic resource]] |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1998] |
| Descrizione fisica | 1 online resource |
| Collana | NRC information notice |
| Soggetto topico |
Nuclear fuel claddings
Oxidation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699793403321 |
| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1998] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Progress on pellet-cladding interaction and stress corrosion cracking : experimentation, modelling and methodologies applied to support the flexible operation of nuclear power plants / / International Atomic Energy Agency
| Progress on pellet-cladding interaction and stress corrosion cracking : experimentation, modelling and methodologies applied to support the flexible operation of nuclear power plants / / International Atomic Energy Agency |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2021] |
| Descrizione fisica | 1 online resource (314 pages) |
| Disciplina | 700 |
| Collana | IAEA TECDOC Series |
| Soggetto topico | Nuclear fuel claddings |
| ISBN |
1-5231-4971-X
92-0-116421-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910794524603321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2021] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Progress on pellet-cladding interaction and stress corrosion cracking : experimentation, modelling and methodologies applied to support the flexible operation of nuclear power plants / / International Atomic Energy Agency
| Progress on pellet-cladding interaction and stress corrosion cracking : experimentation, modelling and methodologies applied to support the flexible operation of nuclear power plants / / International Atomic Energy Agency |
| Pubbl/distr/stampa | Vienna, Austria : , : International Atomic Energy Agency, , [2021] |
| Descrizione fisica | 1 online resource (314 pages) |
| Disciplina | 700 |
| Collana | IAEA TECDOC Series |
| Soggetto topico | Nuclear fuel claddings |
| ISBN |
1-5231-4971-X
92-0-116421-1 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910811136303321 |
| Vienna, Austria : , : International Atomic Energy Agency, , [2021] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Report on ECCS cladding models, NUREG-0630
| Report on ECCS cladding models, NUREG-0630 |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 |
| Descrizione fisica | 1 online resource |
| Collana | Generic letter |
| Soggetto topico |
Emergency core cooling systems
Nuclear fuel claddings |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Report on emergency core cooling system cladding models, NUREG-0630 |
| Record Nr. | UNINA-9910715929703321 |
| Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1980 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Zirconium in the Nuclear Industry
| Zirconium in the Nuclear Industry |
| Autore | Lowe A. L |
| Pubbl/distr/stampa | [Place of publication not identified], : American Society for Testing & Materials, 1977 |
| Descrizione fisica | 1 online resource (677 pages) |
| Disciplina | 621.48335 |
| Soggetto topico | Nuclear fuel claddings |
| ISBN | 0-8031-4705-8 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910164732103321 |
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Lowe A. L
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| [Place of publication not identified], : American Society for Testing & Materials, 1977 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Zirconium in the nuclear industry : 17th international symposium / / editors, Robert Cornstock, Pierre Barbéris
| Zirconium in the nuclear industry : 17th international symposium / / editors, Robert Cornstock, Pierre Barbéris |
| Pubbl/distr/stampa | ASTM International |
| Soggetto topico |
Nuclear fuel claddings
Zirconium alloys |
| ISBN | 0-8031-7580-9 |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Zirconium in the Nuclear Industry |
| Record Nr. | UNINA-9910164683603321 |
| ASTM International | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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