Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak

• Autore: Belaïd S.
• Pubblicazione: Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013
• Descrizione fisica: 1 online resource (xiii, 29 pages) : color illustrations
• Soggetto topico: Pressurized water reactors - Testing; Emergency core cooling systems - Testing; Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement; Nuclear fuel claddings - Effect of temperature on - Measurement; Nuclear power plants - Safety measures - Testing
• Persona (resp. second.): FreixaJ; ZerkakO
• Note generali: Title from title screen (viewed Oct. 25, 2013).; "September 2013."
• Nota di bibliografia: Includes bibliographical references (page 29).
• Altri titoli varianti: Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE
• Titolo autorizzato: Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE
• Formato: Materiale a stampa
• Livello bibliografico: Monografia
• Lingua di pubblicazione: Inglese
• Record Nr.: 9910704812803321
• Lo trovi qui: Univ. Federico II