Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA / / prepared by V.A. Vinogradov, A.Y. Balykin

• Autore: Vinogradov V. A.
• Pubblicazione: Washington, DC : , : Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , April 2001
• Descrizione fisica: 1 online resource (various pagings) : illustrations
• Soggetto topico: Pressurized water reactors - Loss of coolant - Computer simulation
• Persona (resp. second.): BalykinA. Y.
• Note generali: "Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute."; "April 2001."; "Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."; "Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
• Nota di bibliografia: Includes bibliographical references (page 28).
• Titolo autorizzato: Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910706114003321
• Lo trovi qui: Univ. Federico II