Development of a computer tool for in-depth analysis and post processing of the RELAP5 thermal hydraulic code [[electronic resource] /] / R.H. Santos, J. M. Izquierdo Rocha
| Development of a computer tool for in-depth analysis and post processing of the RELAP5 thermal hydraulic code [[electronic resource] /] / R.H. Santos, J. M. Izquierdo Rocha |
| Autore | Santos R. H |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] |
| Descrizione fisica | 1 volume (various pagings) : illustrations |
| Altri autori (Persone) | Izquierdo RochaJ. M |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Computer simulation
Nuclear power plants - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910700376803321 |
Santos R. H
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011] | ||
| Lo trovi qui: Univ. Federico II | ||
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FRAPTRAN-1.5 / / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta
| FRAPTRAN-1.5 / / prepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta |
| Autore | Geelhood K. J. |
| Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 |
| Descrizione fisica | 2 volumes : color illustrations |
| Soggetto topico |
Nuclear fuel rods - Computer simulation
Nuclear fuel rods - Performance - Analysis Nuclear fuel rods - Data processing Nuclear fuel claddings - Data processing Nuclear power plants - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | Vol. 1. A computer code for the transient analysis of oxide fuel rods -- vol. 2. Integral assessment. |
| Record Nr. | UNINA-9910704169803321 |
Geelhood K. J.
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| Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014 | ||
| Lo trovi qui: Univ. Federico II | ||
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Improvements and validation of the system code TRACE for lead and lead-alloy cooled fast reactors safety-related investigations / / prepared by: Wadim Jaeger, Victor Hugo Sanchez Espinoza
| Improvements and validation of the system code TRACE for lead and lead-alloy cooled fast reactors safety-related investigations / / prepared by: Wadim Jaeger, Victor Hugo Sanchez Espinoza |
| Autore | Jaeger Wadim |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2013] |
| Descrizione fisica | 1 online resource (115 unnumbered pages) : colored illustrations |
| Collana | International agreement report |
| Soggetto topico |
Liquid metal fast breeder reactors - Cooling systems - Computer simulation
Nuclear power plants - Computer simulation Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910704460103321 |
Jaeger Wadim
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2013] | ||
| Lo trovi qui: Univ. Federico II | ||
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TRAC-BF1 to TRACE model semi-automatic conversion : PBTT example / / prepared by R. Miró [and four others]
| TRAC-BF1 to TRACE model semi-automatic conversion : PBTT example / / prepared by R. Miró [and four others] |
| Autore | Miró R. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Computer simulation
Nuclear facilities - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC-BF1 to TRACE model semi-automatic conversion |
| Record Nr. | UNINA-9910704268203321 |
Miró R.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015 | ||
| Lo trovi qui: Univ. Federico II | ||
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