Safety Analysis for a Fuel Qualification Test with Supercritical Water (KIT Scientific Reports ; 7682)
Abstract:
A supercritical water cooled reactor (SCWR) is one promising reactor concept selected by the Generation IV International Forum. The design and licensing of such a small-scale fuel assembly with a high pressure coolant loop, involving emergency and auxiliary systems, is the scope of the project SCWR-FQT. In this work, a numerical model of the test facility with all safety-relevant components has been elaborated with the one-dimensional system code APROS.
| Zugehörige Institution(en) am KIT | Institut für Kern- und Energietechnik (IKET) |
| Publikationstyp | Hochschulschrift |
| Publikationsjahr | 2014 |
| Sprache | Englisch |
| Identifikator | ISBN: 978-3-7315-0277-7 urn:nbn:de:0072-434583 KITopen-ID: 1000043458 Reportnummer: KIT-SR 7682 |
| HGF-Programm | 32.21.12 (POF II, LK 01) Thermohydraulik zur Sicherheitsbewertung |
| Verlag | KIT Scientific Publishing |
| Umfang | VI, 126 S. |
| Art der Arbeit | Dissertation |
| Fakultät | Fakultät für Maschinenbau (MACH) |
| Institut | Institut für Kern- und Energietechnik (IKET) |
| Prüfungsdaten | 23.07.2014 |
| Schlagwörter | überkritisches Wasser, Generation IV, Brennstofftest, Sicherheitsanalysen, Sicherheitssysteme, supercritical water, Generation IV, fuel element test, safety analysis, safety systems |
| Relationen in KITopen | |
| Referent/Betreuer | Schulenberg, T. |