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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  
Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2011]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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.  
Washington, D.C. : , : United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , October 2014
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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  
Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2013]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
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.  
Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2015
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui