Assessment of CCFL model of RELAP5/MOD3 against simple vertical tubes and rod bundle tests / / prepared by S. Cho [and three others]

• Autore: Cho S.
• Pubblicazione: Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , June 1993
• Descrizione fisica: 1 online resource (114 pages) : illustrations
• Soggetto topico: Pressurized water reactors - Accidents - Computer simulation; Nuclear fuel rods - Testing
• Note generali: "Korea Electric Power Corporation, Research Center."; "Korea Institute of Nuclear Safety."; "June 1993."; "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP)."; "Type of report: technical"--Bibliographic data sheet.
• Nota di bibliografia: Includes bibliographical references.
• Titolo autorizzato: Assessment of CCFL model of RELAP5
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910708490003321
• Lo trovi qui: Univ. Federico II