The analysis and study of ELAP event and mitigation strategies using TRACE code for Maanshan PWR / / prepared by Jung-Hua Yang [and seven others] |
Autore | Yang Ronghua |
Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 2019 |
Descrizione fisica | 1 online resource (xiii, 31 pages) : illustrations (some color) |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Taiwan - Computer programs
Nuclear power plants - Heating and ventilation - Taiwan |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis and study of Extended Loss of AC Power event and mitigation strategies using TRACE code for Maanshan pressurized water reactor |
Record Nr. | UNINA-9910712082303321 |
Yang Ronghua | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , February 2019 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code / / prepared by Fulvio Mascari [and five others] |
Autore | Mascari Fulvio |
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 reactors - Design and construction
Light water reactors - Design and construction Pressurized water reactors - Design and construction Nuclear reactors - Analysis Nuclear reactors - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis of the OSU MASLWR 001 and 002 tests by using the TRACE code |
Record Nr. | UNINA-9910707643603321 |
Mascari Fulvio | ||
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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Analysis with TRACE code of Rosa test 1.2 : small LOCA in the hot-leg with HPI and accumulator actuation / / prepared by J.L. Munoz-Cobo, A. Romero, S. Chiva |
Autore | Muñoz-Cobo J. L. |
Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2013 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Collana | International agreement report |
Soggetto topico |
Light water reactors - Analysis
Nuclear power plants Nuclear reactors - Thermodynamics Thermal hydraulics |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Analysis with TRACE code of Rosa test 1.2 |
Record Nr. | UNINA-9910704660203321 |
Muñoz-Cobo J. L. | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2013 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Assessment of critical subcooled flow through cracks in large and small pipes using TRACE and RELAP5 / / prepared by Andrew Oussoren, J. Riznic, S.T. Revankar |
Autore | Oussoren Andrew |
Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 |
Descrizione fisica | 1 online resource (xv, 29 pages) : illustrations (some color) |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear power plants - Piping - Cracking |
Soggetto genere / forma | Online resources. |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910706176303321 |
Oussoren Andrew | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Development of a coupled TRACE/PARCS model for KKL and benchmark against the turbine trip test / / prepared by P. Papadopoulos, A. Sekhri |
Autore | Papadopoulos P. |
Pubbl/distr/stampa | Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2017 |
Descrizione fisica | 1 online resource (xv, 37 pages) : illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Safety measures - Computer programs
Pressurized water reactors - Taiwan - Safety measures Pressurized water reactors - Taiwan - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910705687403321 |
Papadopoulos P. | ||
Washington, DC : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2017 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test / / prepared by Byung-Gil Huh, Ae-Ju Cheong, Kyung Won Lee |
Autore | Byung-Gil Huh |
Pubbl/distr/stampa | Washington, D.C. : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 |
Descrizione fisica | 1 online resource (xiv, 131 pages) : illustrations |
Collana | International agreement report |
Soggetto topico |
Pressurized water reactors - Loss of coolant
Nuclear fuel elements - Testing |
Soggetto genere / forma | Online resources. |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti | Evaluation of TRACE spacer grid model with full-length emergency core heat transfer separate effects and systems effects test reflood test |
Record Nr. | UNINA-9910706132303321 |
Byung-Gil Huh | ||
Washington, D.C. : , : Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 2017 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / / prepared by Han-Sik Jung [and four others] |
Autore | Jung Han-Sik |
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 (31 pages) : color illustrations |
Collana | International agreement report |
Soggetto topico |
Nuclear power plants - Piping - Safety measures
Steam-boilers Nuclear reactors - Cooling - Safety measures Nuclear power plants - United States |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910707802803321 |
Jung Han-Sik | ||
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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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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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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