Assessment of LONF ATWS for Maanshan PWR using TRACE code / / prepared by: Jong-Rong Wang [and three others]

• Autore: Wang Jong-Rong
• Pubblicazione: Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014
• Descrizione fisica: 1 online resource (53 unnumbered pages) : color illustrations
• Soggetto topico: Pressurized water reactors - China - Loss of coolant - Computer simulation; Pressurized water reactors - Accidents - China - Computer simulation; Nuclear power plants - China - Computer simulation; Nuclear power plants - China - Safety measures
• Note generali: Title from title screen (viewed March 13, 2014).; "February 2014."; "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 (pages 6-1).
• Altri titoli varianti: Assessment of Loss Of Normal Feedwater Anticipated Transient Without Scram for Maanshan Pressurized Water Reactor using TRAC/RELAP Advanced Computational Engine code
• Titolo autorizzato: Assessment of LONF ATWS for Maanshan PWR using TRACE code
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910705122703321
• Lo trovi qui: Univ. Federico II