Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 / / prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

• Autore: Freixa J.
• Pubblicazione: Washington, DC : , : U.S. Nuclear Regulatory Commission, , October 2014
• Descrizione fisica: 1 online resource (73 unnumbered pages) : color illustrations
• Soggetto topico: Nuclear power plants - Accidents - Computer simulation; Nuclear power plants - Computer programs - Testing; Pressurized water reactors - Loss of coolant - Computer simulation; Nuclear reactor accidents - Computer simulation
• Note generali: Title from title screen (viewed April 8, 2015).; "Manuscript completed: April 2011 ; Date published: October 2014."
• Nota di bibliografia: Includes bibliographical references (page 7-1).
• Titolo autorizzato: Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910703560503321
• Lo trovi qui: Univ. Federico II