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 | ||
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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 | ||
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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 | ||
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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 | ||
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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 | ||
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