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Analysis of the control rod drop accident (CRDA) for lungmen ABWR / / prepared by Chunkuan Shih [and five others]
| Analysis of the control rod drop accident (CRDA) for lungmen ABWR / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear power plants - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the control rod drop accident |
| Record Nr. | UNINA-9910703981503321 |
Shih Chunkuan
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) / / prepared by J.L. Crespo, R.A. Fernández
| Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) / / prepared by J.L. Crespo, R.A. Fernández |
| Autore | Crespo J. L. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (xi, 33 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear reactor accidents - Spain - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Assessment of MSIV full closure for Santa Maria De Garoña nuclear power plant using TRAC-BF1 |
| Record Nr. | UNINA-9910707884003321 |
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Crespo J. L.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of the turbine trip transient in cofrentes NPP with TRAC-BF1 / / prepared by F. Castrillo, A. Gomez, I. Gallego
| Assessment of the turbine trip transient in cofrentes NPP with TRAC-BF1 / / prepared by F. Castrillo, A. Gomez, I. Gallego |
| Autore | Castrillo F. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear reactor accidents - Spain - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910707884403321 |
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Castrillo F.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Characterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident / / prepared by E.R. Lindgren and S.G. Durbin ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
| Characterization of thermal-hydraulic and ignition phenomena in prototypic, full-length boiling water reactor spent fuel pool assemblies after a postulated complete loss-of-coolant accident / / prepared by E.R. Lindgren and S.G. Durbin ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
| Autore | Lindgren Eric R. |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2013 |
| Descrizione fisica | 1 online resource (247 unnumbered pages) : color illustrations |
| Soggetto topico |
Water cooled reactors - Loss of coolant - Computer simulation
Spent reactor fuels - Accidents - Computer simulation Boiling water reactors - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910704404703321 |
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Lindgren Eric R.
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| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) / / prepared by J.V. López, J. L. Crespo, R. A. Fernandez
| Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 (G1J1) / / prepared by J.V. López, J. L. Crespo, R. A. Fernandez |
| Autore | Lopez J. V. |
| Pubbl/distr/stampa | Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1992 |
| Descrizione fisica | 1 online resource (xi, 49 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear reactor accidents - Spain - Computer simulation Nuclear power plants - Accidents - Spain - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Recirculation suction large break LOCA analysis of the Santa Maria De Garoña nuclear power plant using TRAC-BF1 |
| Record Nr. | UNINA-9910707779803321 |
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Lopez J. V.
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| Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 1992 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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State-of-the-Art Reactor Consequence Analyses Project : uncertainty analysis of the unmitigated long-term station blackout of the Peach Bottom Atomic Power Station / / prepared by P. Mattie [and six others]
| State-of-the-Art Reactor Consequence Analyses Project : uncertainty analysis of the unmitigated long-term station blackout of the Peach Bottom Atomic Power Station / / prepared by P. Mattie [and six others] |
| Autore | Matthiae Paolo |
| Pubbl/distr/stampa | Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , May 2016 |
| Descrizione fisica | 1 online resource (621 unnumbered pages) : color illustrations |
| Soggetto topico |
Nuclear power plants - Pennsylvania - Safety measures
Nuclear power plants - Accidents - Computer simulation Boiling water reactors - Accidents - Computer simulation Nuclear reactors - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | State-of-the-Art Reactor Consequence Analyses Project |
| Record Nr. | UNINA-9910707105503321 |
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Matthiae Paolo
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| Washington, DC : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , May 2016 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Soggetto topico
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Boiling water reactors - Accidents - Computer simulation
(6)
- Nuclear reactor accidents - Spain - Computer simulation (3)
- Nuclear power plants - Accidents - Computer simulation (1)
- Nuclear power plants - Accidents - Spain - Computer simulation (1)
- Nuclear power plants - Pennsylvania - Safety measures (1)