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Detail CFD simulation of the integrated reactor pressure vessel of SMART

Böttcher, Michael 1; Sanchez-Espinoza, Victor ORCID iD icon 1
1 Institut für Neutronenphysik und Reaktortechnik (INR), Karlsruher Institut für Technologie (KIT)

Abstract:

This paper presents a detailed analysis of the full Reactor Pressure Vessel (RPV) of SMART with ANSYS CFX 20.2. SMART is a water-cooled SMR designed by KAERI for an operation with forced convection. The thermal power of SMART amounts to 330 MW$_{th}$. In the integrated SMR-concept, the main primary loop components such as the helical steam generators, pressurizer and canned pumps are located inside the RPV. The CFD model uses a concept of full geometrical detail resolution with partial boundary inflation of the mesh and porous media modelling with sources for momentum and energy for components like the core, pumps and steam generators. The detailed results obtained with a steady-state RANS simulation using ANSYS CFX 20.2 are very promising as the comparison of selected core parameters of the CFD-simulation with the ones of the system thermal hydraulic code TRACE have shown.


Verlagsausgabe §
DOI: 10.5445/IR/1000161957
Veröffentlicht am 06.09.2023
Originalveröffentlichung
DOI: 10.1016/j.pnucene.2023.104854
Scopus
Zitationen: 3
Web of Science
Zitationen: 1
Dimensions
Zitationen: 2
Cover der Publikation
Zugehörige Institution(en) am KIT Institut für Neutronenphysik und Reaktortechnik (INR)
Publikationstyp Zeitschriftenaufsatz
Publikationsmonat/-jahr 10.2023
Sprache Englisch
Identifikator ISSN: 0149-1970, 1878-4224
KITopen-ID: 1000161957
HGF-Programm 32.12.01 (POF IV, LK 01) Design Basis Accidents and Materials Research
Erschienen in Progress in Nuclear Energy
Verlag Elsevier
Band 164
Seiten Art.-Nr.: 104854
Vorab online veröffentlicht am 23.08.2023
Schlagwörter CFD, SMART, SMR, Thermal hydraulic analysis, TRACE
Nachgewiesen in Scopus
Web of Science
Dimensions
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