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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]
| 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
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others]
| Thermal hydraulic and fuel rod mechanical combination analysis of Kuosheng Nuclear Power Plant with RELAP5 MOD3.3/FRAPTRAN/Python in SNAP interface / / prepared by Jong-Rong Wang [and five others] |
| Autore | Wang Jong-Rong |
| 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 (xv, 45 pages) : illustrations |
| 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-9910708659903321 |
|
Wang Jong-Rong
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| 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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TRACE analysis on heat removal decrease accidents for AP1000 / / prepared by: Jong-Rong Wang ... [and three others]
| TRACE analysis on heat removal decrease accidents for AP1000 / / 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 |
Pressurized water reactors - Taiwan - Safety measures
Pressurized water reactors - Taiwan - Testing Nuclear power plants - Safety measures - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC/RELAP Advanced Computational Engine analysis on heat removal decrease accidents for AP1000 |
| Record Nr. | UNINA-9910705253303321 |
|
Wang Jong-Rong
|
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
| ||
TRACE simulation of SBO accident and mitigation strategy in Maanshan PWR / / prepared by: Jong-Rong Wang ... [and three others]
| TRACE simulation of SBO accident and mitigation strategy in Maanshan PWR / / prepared by: Jong-Rong Wang ... [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (57 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear power plants - Accidents - Taiwan - Computer simulation
Pressurized water reactors - Taiwan - Safety measures Pressurized water reactors - Taiwan - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | TRAC/RELAP Advance Computational Engine simulation of Steam Blackout accident and mitigation strategy in Maanshan PWR |
| Record Nr. | UNINA-9910704812903321 |
|
Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline / / prepared by Jong-Rong Wang [and six others]
| TRACE/SNAP model establishment of Chinshan nuclear power plant for ultimate response guideline / / prepared by Jong-Rong Wang [and six others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2017 |
| Descrizione fisica | 1 online resource (xv, 49 pages) : illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Boiling water reactors - Taiwan - Evaluation
Nuclear power plants - Taiwan Boiling water reactors - Taiwan - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705749203321 |
|
Wang Jong-Rong
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 2017 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / prepared by Jong-Rong Wang [and three others]
| Uncertainty analysis for Maanshan LBLOCA by TRACE and DAKOTA / / 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 (53 unnumbered pages) : color illustrations |
| Collana | NUREG/IA |
| Soggetto topico |
Nuclear reactor accidents - Analysis
Nuclear reactor accidents - Computer simulation Pressurized water reactors - Loss of coolant - Analysis |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910702555803321 |
|
Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Using SNAP/RADTRAD and HABIT to establish the analysis methodology for Maanshan PWR / / prepared by Jong-Rong Wang [and eight others]
| Using SNAP/RADTRAD and HABIT to establish the analysis methodology for Maanshan PWR / / prepared by Jong-Rong Wang [and eight others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2019 |
| Descrizione fisica | 1 online resource (1 volume (various pagings)) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Taiwan
Nuclear power plants - Taiwan - Control rooms Nuclear power plants - Control rooms Pressurized water reactors |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Using Symbolic Nuclear Analysis Package/RADionuclide, Transport, Removal and Dose Estimation and HABITability to establish the analysis methodology for Maanshan pressurized water reactor |
| Record Nr. | UNINA-9910711995103321 |
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Wang Jong-Rong
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| Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , January 2019 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool / / prepared by Jong-Rong Wang [and nine others]
| Using TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool / / prepared by Jong-Rong Wang [and nine others] |
| Autore | Wang Jong-Rong |
| 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, 33 pages) : illustrations (some color) |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Taiwan - Evaluation
Nuclear power plants - Taiwan Boiling water reactors - Taiwan - Computer simulation Spent reactor fuels - Storage - Taiwan |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910711512503321 |
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Wang Jong-Rong
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| 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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