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Advanced Multi-Physics Methods for Safety Investigations of Research Reactors

Almachi Nacimba, Juan Carlos 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract (englisch):

The main objective of this thesis is to develop an analysis tool for plate-type research reactors capable of performing steady-state and transient calculations using a multiphysics approach between neutronics and thermal-hydraulics. Most research reactors have been licensed using legacy codes that have been developed specifically for those particular reactors. These codes are de¬signed with low-level solutions, which means that certain limitations may exist in terms of accuracy and modeling capabilities. However, in recent years there has been a push to promote the use of more advanced codes, with more mature and highly validated architectures, which are used in power reactor analysis. While the application of these codes to research reactors allows the simulation of steady-state and transient problems, based on heuristic methods and simplifications, the results do not represent all the complexities and details of a real model. In addition, another drawback is that, in many cases, when extended or modified codes are used in research reactors, the verification and validation process is approached in a superficial manner. This implies that a thorough evaluation of the accuracy and reliability of the results obtained is not carried out. ... mehr


Volltext §
DOI: 10.5445/IR/1000169070
Veröffentlicht am 15.03.2024
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Hochschulschrift
Publikationsdatum 15.03.2024
Sprache Englisch
Identifikator KITopen-ID: 1000169070
HGF-Programm 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Verlag Karlsruher Institut für Technologie (KIT)
Umfang xviii, 148 S.
Art der Arbeit Dissertation
Fakultät Fakultät für Maschinenbau (MACH)
Institut Institut für Neutronenphysik und Reaktortechnik (INR)
Prüfungsdatum 18.12.2023
Schlagwörter Serpent2/Subchanflow, Thermal-Hydraulic, Neutronics, Heat transfer, Heat conduction, MTR-plates
Referent/Betreuer Stieglitz, Robert
Margulis, Marat
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