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Main steam line break analysis for Lungmen ABWR / / prepared by Chunkuan Shih [and five others]
Main steam line break analysis for Lungmen ABWR / / prepared by Chunkuan Shih [and five others]
Autore Shih Chunkuan
Pubbl/distr/stampa Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016
Descrizione fisica 1 online resource (xiii, 24 pages) : illustrations
Collana International agreement report
Soggetto topico Nuclear fuel rods
Nuclear pressure vessels
Boiling water reactors
Nuclear power plants - Taiwan - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910709689003321
Shih Chunkuan  
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , November 2016
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
RELAP5/MOD3.3 model assessment and hypothetical accident analysis of Kuosheng Nuclear Power Plant with SNAP interface / / prepared by Chunkuan Shih [and six others]
RELAP5/MOD3.3 model assessment and hypothetical accident analysis of Kuosheng Nuclear Power Plant with SNAP interface / / prepared by Chunkuan Shih [and six others]
Autore Shih Chunkuan
Pubbl/distr/stampa Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , March 2016
Descrizione fisica 1 online resource (89 unnumbered pages) : color illustrations
Collana International agreement report
Soggetto topico Nuclear power plants - Environmental aspects - Taiwan
Nuclear power plants - Taiwan
Nuclear power plants - Taiwan - Evaluation
Nuclear power plants - Taiwan - Safety measures
Nuclear power plants - Taiwan - Computer programs
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910707043303321
Shih Chunkuan  
Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , March 2016
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
RELAP5/MOD3.3 model assessment of Maanshan Nuclear Power Plant with SNAP interface / / prepared by Chunkuan Shih [and five others.]
RELAP5/MOD3.3 model assessment of Maanshan Nuclear Power Plant with SNAP interface / / prepared by Chunkuan Shih [and five others.]
Autore Shih Chunkuan
Pubbl/distr/stampa Washington, D.C. : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , October 2017
Descrizione fisica 1 online resource (various pagings) : color illustrations
Collana International agreement report
Soggetto topico Nuclear power plants - Taiwan - Evaluation
Nuclear power plants - Taiwan - Safety measures
Nuclear power plants - Taiwan - Computer programs
Nuclear power plants
Nuclear power plants - Computer programs
Nuclear power plants - Evaluation
Nuclear power plants - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910712006903321
Shih Chunkuan  
Washington, D.C. : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission, , October 2017
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE / / prepared by: Jong-Rong Wang [and three others]
Sensitivity study of the DEG LBLOCA transient on the counter-current flow limitation by using TRACE / / prepared by: Jong-Rong Wang [and three others]
Autore Wang Jong-Rong
Pubbl/distr/stampa Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014
Descrizione fisica 1 online resource (45 unnumbered pages) : color illustrations
Collana International agreement report
Soggetto topico Water cooled reactors - Taiwan - Loss of coolant - Computer simulation
Boiling water reactors - Accidents - Taiwan - Computer simulation
Nuclear power plants - Taiwan - Computer simulation
Nuclear power plants - Taiwan - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Altri titoli varianti Sensitivity study of the Double-Ended Guillotine Large Break Loss Of Coolant Accident transient on the counter-current flow limitation by using TRAC/RELAP Advanced Computational Engine code
Record Nr. UNINA-9910705122403321
Wang Jong-Rong  
Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui
Spent fuel pool safety analysis of TRACE in Chinshan NPP / / prepared by Chunkuan Shih [and five others]
Spent fuel pool safety analysis of TRACE in Chinshan NPP / / prepared by Chunkuan Shih [and five others]
Autore Shih Chunkuan
Pubbl/distr/stampa Washington, DC : , : U.S. Nuclear Regulatory Commission, , March 2015
Descrizione fisica 1 online resource (69 unnumbered pages) : color illustrations
Collana International agreement report
Soggetto topico Spent reactor fuels - Risk assessment - Taiwan
Spent reactor fuels - Taiwan - Safety measures
Radioactive substances - Storage - Taiwan
Spent reactor fuels - Storage - Taiwan
Nuclear power plants - Taiwan - Safety measures
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UNINA-9910703637103321
Shih Chunkuan  
Washington, DC : , : U.S. Nuclear Regulatory Commission, , March 2015
Materiale a stampa
Lo trovi qui: Univ. Federico II
Opac: Controlla la disponibilità qui