Download Intro_MCS
CORE
School of Mechanical and Nuclear Engineering
MCS
Introduction
A Monte Carlo code MCS has being developed at Ulsan National Institute of Science and Technology (UNIST) since 2013. The target of MCS is to solve complex whole core problems like BEAVRS. MCS can treat the 3D whole core geometry with universe and lattice, and the neutron physics 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
• 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
– 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
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
