Neutron Transport in Hexagonal Reactor Cores Modeled by Trigonal-Geometry Diffusion and Simplified P3 Nodal Methods
Abstract:
The superior advantage of a nodal method for reactor cores with hexagonal fuel assemblies discretized as cells consisting of equilateral triangles is its mesh refinement capability. In this thesis, a diffusion and a simplified P3 (or SP3) neutron transport nodal method are developed based on trigonal geometry.
| Zugehörige Institution(en) am KIT | Institut für Neutronenphysik und Reaktortechnik (INR) |
| Publikationstyp | Hochschulschrift |
| Publikationsjahr | 2013 |
| Sprache | Englisch |
| Identifikator | urn:nbn:de:swb:90-348700 KITopen-ID: 1000034870 |
| HGF-Programm | 32.02.01 (POF II, LK 01) |
| Verlag | Karlsruher Institut für Technologie (KIT) |
| Art der Arbeit | Dissertation |
| Prüfungsdaten | 15.04.2013 |
| Schlagwörter | SP3, simplified P3, nodal method, trigonal, hexagonal |
