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Introduction The Monte Carlo code MCS is under developement at Ulsan National Institute of Science and Technology (UNIST) since 2013. The target of MCS is to solve complex whole-core problems with high-fidelity and high-performance, through the use of multi-physics coupling with thermal-hydraulic and fuel performance codes, On-The-Fly Doppler broadening of neutron cross-sections and depletion module. Basic capabilities of MCS include treatment of 3D whole core geometry with universe and lattice and neutron physics treatment with probability-table, free-gas treatment, S(a,b) and Doppler broadening Rejection Correction. Overview Monte Carlo Code MCS • Language: Fortran 2003 • Purpose - Large Scale Reactor Analysis with accelerated Monte Carlo simuation - University research: MC methodology development, advanced reactor design • General 3-D geometry • Nuclear Data - ENDF-B/VII.0 and ENDF-B/VII.1 - Continuous energy and multi-group - Double indexing method • Physics - Resonance upscattering (DBRC, FESK) - Probability table method - S(𝜶,𝜷) - On the fly Doppler broadening - CTF Coupling • Acceleration - MOC and MC Hybrid solver - Modified power iteration - Wielandt method - CMFD • Parallelism - Parallel fission bank • Depletion - CRAM , MEM, Krylov Subspace • Multi-physics coupling - CTF/FRAPCON CORE Benchmark  BEAVRS HFP at BOC Normalized fission reaction rate and flux  Fuel temperature and coolant density  BEAVRS Cycle 1 Whole Core Depletion with Full Feedback Flow Chart  BEAVRS TH Calculation with depletion effect  BEAVRS Cycle 1 & Cycle 2  MCS/CTF/FRAPCON Multi-physics Coupling Code System   |
4. Code Development >