Analysis of the control rod drop accident (CRDA) for lungmen ABWR / / prepared by Chunkuan Shih [and five others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 |
Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear power plants - Safety measures |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis of the control rod drop accident |
Record Nr. | UNINA-9910703981503321 |
Shih Chunkuan | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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BEPU analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA / / prepared by Chunkuan Shih [and five others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , September 2015 |
Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear reactor accidents - Analysis
Pressurized water reactors - Loss of coolant - Computer simulation Nuclear power plants - Licenses Nuclear power plants - Accidents - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Best Estimate Plus Uncertainty analysis and benchmark with IIST 2% SBLOCA experiment using TRACE/DAKOTA |
Record Nr. | UNINA-9910704055603321 |
Shih Chunkuan | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , September 2015 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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The development and application of Kuosheng (BWR/6) nuclear power plant TRACE/SNAP model / / prepared by Chunkuan Shih [and five others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2014 |
Descrizione fisica | 1 online resource (77 unnumbered pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Taiwan
Boiling water reactors - Taiwan Boiling water reactors - Taiwan - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Development and application of Kuosheng |
Record Nr. | UNINA-9910703560403321 |
Shih Chunkuan | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , December 2014 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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The establishment and assessment of Kuosheng (BWR/6) NPP dry-storage system TRACE/SNAP model / / prepared by Chunkuan Shih [and three others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , January 2015 |
Descrizione fisica | 1 online resource (57 unnumbered pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Taiwan
Spent reactor fuels - Storage - Taiwan Radioactive substances - Storage - Taiwan Boiling water reactors - Taiwan Boiling water reactors - Taiwan - Computer simulation |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Establishment and assessment of Kuosheng |
Record Nr. | UNINA-9910703560303321 |
Shih Chunkuan | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , January 2015 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / 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, , August 2016 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear fuel rods
Nuclear reactor accidents - Analysis Pressurized water reactors - Loss of coolant - Analysis Nuclear power plants - Taiwan |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910707412703321 |
Shih Chunkuan | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , August 2016 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface / / prepared by Chunkuan Shih [and six others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , March 2016 |
Descrizione fisica | 1 online resource (93 unnumbered pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Taiwan
Nuclear fuel rods - Thermal properties - Computer programs |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910707042303321 |
Shih Chunkuan | ||
Washington, DC : , : U.S. Nuclear Regulatory Commission, , March 2016 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP / / prepared by Chunkuan Shih [and six others] |
Autore | Shih Chunkuan |
Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2018 |
Descrizione fisica | 1 online resource (xv, 59 pages) : illustrations (some color) |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Taiwan - Computer programs
Pressurized water reactors - Loss of coolant |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP5 Symbolic Nuclear Analysis Program |
Record Nr. | UNINA-9910711783803321 |
Shih Chunkuan | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , October 2018 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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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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Main stream 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, , June 2016 |
Descrizione fisica | 1 online resource (xiii, 24 pages) : illustrations + + errata |
Collana | International agreement report |
Soggetto topico |
Nuclear reactor accidents - Computer simulation
Nuclear fuel rods - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910708659703321 |
Shih Chunkuan | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 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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