Development and validation of multiphysics PWR core simulator KANT

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KANT (KAIST Advanced Nuclear Tachygraphy) is a PWR core simulator recently developed at Korea Advance Institute of Science and Technology, which solves three-dimensional steady-state and transient multigroup neutron diffusion equations under Cartesian geometries alongside the incorporation thermal-hydraulics feedback effect for multi-physics calculation. It utilizes the standard Nodal Expansion Method (NEM) accelerated with various Coarse Mesh Finite Difference (CMFD) methods for neutronics calculation. For thermal-hydraulics (TH) calculation, a single-phase flow model and a one-dimensional cylindrical fuel rod heat conduction model are employed. The time-dependent neutronics and TH culations are numerically solved through an implicit Euler scheme, where a detailed coupling strategy presented in this paper alongside a description of nodal equivalence, macroscopic depletion, and power reconstruction. For validation of the steady, transient, and depletion calculation with pin power reconstruction capacity of KANT, solutions for various benchmark problems are presented. The IAEA 3-D PWR and 4-group KOEBERG problems were considered for the steady-state reactor benchmark problem. For transient calculations, LMW (Lagenbuch, Maurer and Werner) LWR and NEACRP 3-D PWR bench-marks were solved, where the latter problem includes thermal-hydraulics feedback. For macroscopic depletion with pin power reconstruction, a small PWR problem modified with KAIST benchmark model was solved. For validation of the multi-physics analysis capability of KANT concerning large-sized PWRs, the BEAVRS Cycle1 benchmark has been considered. It was found that KANT solutions are accurate and consistent compared to other published works.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
Publisher
KOREAN NUCLEAR SOC
Issue Date
2023-06
Language
English
Article Type
Article
Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.55, no.6, pp.2230 - 2245

ISSN
1738-5733
DOI
10.1016/j.net.2023.02.025
URI
http://hdl.handle.net/10203/307425
Appears in Collection
NE-Journal Papers(저널논문)
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