Info
- Utilizzare la checkbox di selezione a fianco di ciascun documento per attivare le funzionalità di stampa, invio email, download nei formati disponibili del (i) record.
The analysis and study of ELAP event and mitigation strategies using TRACE code for Maanshan PWR / / prepared by Jung-Hua Yang [and seven others]
| 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 | ||
| ||
Analysis of the OSU-MASLWR 001 and 002 tests by using the TRACE code / / prepared by Fulvio Mascari [and five others]
| 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 | ||
| ||
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
| 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 | ||
| ||
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
| 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 | ||
| ||
Development of a coupled TRACE/PARCS model for KKL and benchmark against the turbine trip test / / prepared by P. Papadopoulos, A. Sekhri
| 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 | ||
| ||
Evaluation of TRACE spacer grid model with FLECHT-SEASET reflood test / / prepared by Byung-Gil Huh, Ae-Ju Cheong, Kyung Won Lee
| 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 | ||
| ||
Feedwater line break analysis using RELAP5/MOD3.3 for steam generator blowdown load assessment / / prepared by Han-Sik Jung [and four others]
| 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 | ||
| ||
Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others]
| 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 | ||
| ||
Loss of flow analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP / / prepared by Chunkuan Shih [and six others]
| 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 | ||
| ||
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 | ||
| ||
