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.
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
• Prallelism
– Parallel fission bank
• Depletion
– CRAM , MEM, Krylov Subspace
CORE Benchmark
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
