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Analysis and computational predictions of CHF position and post-CHF heat transfer [[electronic resource] /] / prepared by B. Belhouachi, S.P. Walker, G.F. Hewitt
Analysis and computational predictions of CHF position and post-CHF heat transfer [[electronic resource] /] / prepared by B. Belhouachi, S.P. Walker, G.F. Hewitt
Autore Belhouachi B
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (30 pages (various pagings)) : illustrations (some color)
Altri autori (Persone) WalkerS. P
HewittG. F (Geoffrey Frederick)
CalvoA
Collana International agreement report
Soggetto topico Pressurized water reactors - Critical heat flux - Computer simulation
Trace elements - Analysis - Computer simulation
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910697125903321
Belhouachi B  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Analysis of a loss of normal feedwater transient at the Ringhals-3 NPP using RELAP5/Mod3.3 [[electronic resource] /] / prepared by: J. Bánáti, C. Demaziére, and M. Stålek
Analysis of a loss of normal feedwater transient at the Ringhals-3 NPP using RELAP5/Mod3.3 [[electronic resource] /] / prepared by: J. Bánáti, C. Demaziére, and M. Stålek
Autore Bánáti J (Jozsef)
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (58 pages) : illustrations (some color), color map
Altri autori (Persone) DemaziéreC
StålekM
CalvoA
Collana International agreement report
Soggetto topico Pressurized water reactors - Control - Analysis
Nuclear power plants - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910699322803321
Bánáti J (Jozsef)  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Assessment of RELAP5/MOD3.3Beta code for the LOFT Experiment L9-1/L3-3 [[electronic resource] /] / prepared by: Kyu Bok Lee ... [and others]
Assessment of RELAP5/MOD3.3Beta code for the LOFT Experiment L9-1/L3-3 [[electronic resource] /] / prepared by: Kyu Bok Lee ... [and others]
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (97 pages) : illustrations
Altri autori (Persone) LeeKyu Bok
CalvoA
Collana International agreement report
Soggetto topico Nuclear reactor accidents - Evaluation
Nuclear power plants - Accidents - Evaluation
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910697290803321
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant [[electronic resource] /] / prepared by: Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
Assessment of the TRACE code using transient data from Maanshan PWR Nuclear Power Plant [[electronic resource] /] / prepared by: Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
Autore Wang Jong-Rong
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (54 pages) : illustrations (some color)
Altri autori (Persone) LinHao-Tzu
ShihChunkuan
CalvoA
Collana International agreement report
Soggetto topico Nuclear power plants - Instruments - Control
Nuclear engineering - Instruments
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910699323303321
Wang Jong-Rong  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Assessment of the turbine trip transient in Santa Maria de Garoña Nuclear Power Plant with TRACE version 4.16 [[electronic resource] /] / prepared by: P. Corcuera, E. Rodríguez, G. Villescas
Assessment of the turbine trip transient in Santa Maria de Garoña Nuclear Power Plant with TRACE version 4.16 [[electronic resource] /] / prepared by: P. Corcuera, E. Rodríguez, G. Villescas
Autore Corcuera P
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (46 pages) : illustrations
Altri autori (Persone) RodríguezE
VillescasG
CalvoAntony
Collana International agreement report
Soggetto topico Nuclear reactor accidents - Spain - Computer simulation
Nuclear engineering - Spain - Instruments - Computer simulation
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910697046503321
Corcuera P  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
An assessment of TRACE V4.160 code against PACTEL ATWS-10 - 13 and ATWS-20 - 21 pressurizer experiments [[electronic resource] /] / prepared by: E. Takasuo
An assessment of TRACE V4.160 code against PACTEL ATWS-10 - 13 and ATWS-20 - 21 pressurizer experiments [[electronic resource] /] / prepared by: E. Takasuo
Autore Takasuo E
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (vii, 23, 18 pages) : illustrations
Altri autori (Persone) CalvoA
Collana International agreement report
Soggetto topico Pressurized water reactors - Control - Simulation methods
Nuclear engineering - Instruments - Simulation methods
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910697291203321
Takasuo E  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
An assessment of TRACE V4.160 code against PACTEL LOF-10 experiment [[electronic resource] /] / prepared by: J. Vihavainen
An assessment of TRACE V4.160 code against PACTEL LOF-10 experiment [[electronic resource] /] / prepared by: J. Vihavainen
Autore Vihavainen J (Juhani)
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (151 pages) : illustrations (some color)
Altri autori (Persone) CalvoA
Collana International agreement report
Soggetto topico Pressurized water reactors - Control - Analysis
Nuclear engineering - Instruments - Analysis
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910699323003321
Vihavainen J (Juhani)  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP / / prepared by B. Arsenault [and five others]
Benchmarking of a generic CANDU reactor with PARCS, MCNP and RFSP / / prepared by B. Arsenault [and five others]
Autore Arsenault B.
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , September 2015
Descrizione fisica 1 online resource (93 unnumbered pages) : color illustrations
Collana International agreement report
Soggetto topico CANDU reactors - Computer simulation - Quality control
Heavy water reactors - Computer simulation - Quality control
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910704091503321
Arsenault B.  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , September 2015
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA / / prepared by: Jong-Rong Wang [and three others]
The development and assessment of TRACE model for Maanshan Nuclear Power Plant LOCA / / prepared by: Jong-Rong Wang [and three others]
Autore Wang Jong-Rong
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2012]
Descrizione fisica 1 online resource (49 pages) : colored illustrations
Collana International agreement report
Soggetto topico Pressurized water reactors - China - Loss of coolant - Computer simulation
Pressurized water reactors - Accidents - China - Computer simulation
Nuclear power plants - China - Computer simulation
Nuclear power plants - China - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Altri titoli varianti Development and assessment of TRAC/RELAP Advanced Computational Engine model for Maanshan PWR Nuclear Power Plant Loss of Coolant Accident
Record Nr. UNINA-9910704351103321
Wang Jong-Rong  
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2012]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others]
Development of horizontal off-take model for application to reactor headers of CANDU type reactors [[electronic resource] /] / prepared by: Yong Jin Cho ... [and others]
Pubbl/distr/stampa Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Descrizione fisica 1 online resource (61 pages) : illustrations
Altri autori (Persone) ChoYŏng-jin
CalvoA
Collana International agreement report
Soggetto topico CANDU reactors - Accidents - Analysis
Nuclear reactor accidents - Analysis
Nuclear reactors - Fluid dynamics - Models
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910699323103321
Washington, DC : , : U. S. Nuclear Regulatory Commission, , [2010]
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui