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Introduction
The RASTK-F code is under further development at the Ulsan National Institute of Science and Technology (UNIST) for the hexagonal-z geometry including the extension of two-group rectangular solver to multi-group hexagonal solver and the update of thermal-physical properties of fast reactor core materials in the internal thermal-hydraulic solver. The triangle-based polynomial expansion nodal (TPEN) method is implemented in the code to solve the multi-group neutron diffusion equation in the 3D hexagonal-z geometry. The change of nuclide concentrations during burnup steps are determined by solving Bateman equation. At present, Chebyshev Rational Approximation Method (CRAM) is implemented in nodal diffusion code RAST-K and is adopted for fast reactor with hexagonal lattice (RASTK-HEX). Acceleration of the RASTK-F depletion solver by GPU is also under interrogation. The required 24 energy group cross section set for RASTK-HEX can be generated using our in-house Monte Carlo code MCS. Neutronics – Triangle-based Polynomial Expansion Nodal method (TPEN) – CMFD acceleration XS model – Multi-group group constants from STREAM2D – Micro XS for micro depletion TH feedback – 1D radial heat conduction Fuel cycle analysis – Micro-depletion for 28 actinides and 193 fission products – CRAM depletion solver – Sparse Gauss-Seidel Solver – Predictor/corrector – Triangle depletion Engineering Features – Multi-cycle calculation (shuffling, rotation) – Restart calculation The RASTK-F is verified by MCS with an in-house design of a SMLFR  |
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