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Improved methodologies for evaluation of severe transient conditions of sodium-cooled fast systems

Ponomarev, Alexander

Abstract (englisch):

The work is dedicated to the analysis and improvements of methodologies of safety evaluations of Sodium-cooled Fast Reactor (SFR) systems. In particular, the work is built around the SAS-SFR code which is primarily used for the deterministic analysis of the Initiation Phase (IP) of severe accidents in SFRs. It provides comprehensive thermal hydraulics and fuel pin mechanics simulation models for the prediction of steady state characterization of fuel pin configuration during fuel pin burnup cycle and subsequent accident transient behaviour of the entire SFR core including core material melting and relocation phenomena should the fuel pin configuration fail.
Based on existing well-validated computational tools and models for neutron physics, the work aims to improve the existing SAS-SFR capabilities by the application of advanced neutron physics simulation approaches. With regard to the modelling of the IP phenomenology, one important limitation of the currently applied SAS-SFR code is the use of the Point Kinetics (PK) model which considers fixed normalised spatial shape of the core power and neutron flux for the whole range of the simulation time. ... mehr

Volltext §
DOI: 10.5445/IR/1000069106
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Hochschulschrift
Publikationsjahr 2017
Sprache Englisch
Identifikator urn:nbn:de:swb:90-691061
KITopen-ID: 1000069106
HGF-Programm 32.02.01 (POF III, LK 01) Sicherheitsanalysen: Anlagendynamik
Verlag Karlsruher Institut für Technologie (KIT)
Umfang 168 S.
Art der Arbeit Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Karlsruher Institut für Technologie (KIT)
Prüfungsdatum 21.03.2017
Schlagwörter Sodium-cooled Fast Reactor (SFR), Generation IV, ESFR, SAS-SFR, PARCS, MCNP, coupled thermal-hydraulics and neutron physics simulations, Monte Carlo neutron transport, spatial kinetics, safety analysis, ULOF, Initiation Phase, fuel and clad relocation
Referent/Betreuer Stieglitz, R.
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