Fuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA / / prepared by Chunkuan Shih [and five others]

• Autore: Shih Chunkuan
• Pubblicazione: 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
• Soggetto topico: Nuclear fuel rods; Nuclear reactor accidents - Analysis; Pressurized water reactors - Loss of coolant - Analysis; Nuclear power plants - Taiwan
• Note generali: "Institute of Nuclear Engineering and Science, National Tsing Hua University, Nuclear and New Energy Education and Research Foundation."; "Department of Nuclear Safety, Taiwan Power Company."; "K. Tien, NRC project manager."; "Manuscript completed: March 2016; date published: August 2016."; "Prepared as part of the agreement on research participation and technical exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
• Nota di bibliografia: Includes bibliographical references.
• Titolo autorizzato: Fuel rod behavior and uncertainty analysis by FRAPTRAN
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910707412703321
• Lo trovi qui: Univ. Federico II