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Analysis of ultimate-heat-sink spray ponds / / R. Codell
| Analysis of ultimate-heat-sink spray ponds / / R. Codell |
| Autore | Codell R (Richard) |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , August 1981 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Heat sinks (Electronics)
Cooling ponds - Measurement - Computer programs Evaporation (Meteorology) - Computer programs Cooling ponds - Climatic factors |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of ultimate heat sink spray ponds |
| Record Nr. | UNINA-9910705604203321 |
Codell R (Richard)
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| Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , August 1981 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Assessment of soil amplification of earthquake ground motion using the "CARES" code version 1.2 / / prepared by R. Pichumani
| Assessment of soil amplification of earthquake ground motion using the "CARES" code version 1.2 / / prepared by R. Pichumani |
| Autore | Pichumani R. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , September 2001 |
| Descrizione fisica | 1 online resource (xii, 32 pages) : illustrations |
| Soggetto topico |
Soil dynamics - Computer simulation
Nuclear power plants - Earthquake effects - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708667403321 |
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Pichumani R.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , September 2001 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Evaluation of available data for probabilistic risk assessments (PRA) of fire events at nuclear power plants / / prepared by L.M. Krasner [and four others]
| Evaluation of available data for probabilistic risk assessments (PRA) of fire events at nuclear power plants / / prepared by L.M. Krasner [and four others] |
| Autore | Samanta P. K. |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 1985 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations |
| Soggetto topico |
Nuclear facilities - Fires and fire prevention - United States
Probabilities Fire detectors Fire extinction |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Evaluation of available data for probabilistic risk assessments |
| Record Nr. | UNINA-9910706777403321 |
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Samanta P. K.
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| Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 1985 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Functional capability of piping systems / / D. Terao, E.C. Rodabaugh
| Functional capability of piping systems / / D. Terao, E.C. Rodabaugh |
| Autore | Terao D. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , November 1992 |
| Descrizione fisica | 1 online resource (vii, 62 pages) : illustrations |
| Soggetto topico |
Nuclear power plants - Piping - United States - Testing
Structural dynamics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705691403321 |
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Terao D.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , November 1992 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Pipe cracking in U.S. BWRs : a regulatory history / / prepared by J.R. Strosnider, Jr. [and three others]
| Pipe cracking in U.S. BWRs : a regulatory history / / prepared by J.R. Strosnider, Jr. [and three others] |
| Autore | Strosnider Jr J.R. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 2000 |
| Descrizione fisica | 1 online resource (various pagings) |
| Soggetto topico |
Boiling water reactors - Piping - Corrosion
Pipelines - Corrosion |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Pipe cracking in U.S. BWRs |
| Record Nr. | UNINA-9910708658303321 |
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Strosnider Jr J.R.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Probability-based evaluation of selected fire protection features in nuclear power plants / / M.A. Azarm, J. L. Boccio
| Probability-based evaluation of selected fire protection features in nuclear power plants / / M.A. Azarm, J. L. Boccio |
| Autore | Azarm M. |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 1985 |
| Descrizione fisica | 1 online resource (xiv, 73, A-3 pages) : illustrations |
| Soggetto topico |
Nuclear facilities - Fires and fire prevention - United States
Fire extinction - Reliability Fires - United States - Mathematical models |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Probability based evaluation of selected fire protection features in nuclear power plants |
| Record Nr. | UNINA-9910706777503321 |
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Azarm M.
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| Washington, D.C. : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , May 1985 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Reactor pressure vessel status report / / C. E. Carpenter [and ten others]
| Reactor pressure vessel status report / / C. E. Carpenter [and ten others] |
| Autore | Carpenter C. E. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , October 2000 |
| Descrizione fisica | 1 online resource (various pagings) |
| Soggetto topico |
Nuclear pressure vessels - Materials - Effect of radiation on
Steel - Effect of radiation on Steel - Embrittlement Fracture mechanics |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910708246903321 |
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Carpenter C. E.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , October 2000 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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