The TRITON reactor physics sequence in SCALE enables time-dependent simulation of nuclide transmutation in models of varying complexity by coupling SCALE’s neutron transport solvers with the depletion and decay code ORIGEN. TRITON automates the entire workflow––nuclear data processing, neutron transport calculations, nuclide depletion and decay––to estimate key quantities such as nuclide compositions, mixture-specific powers, neutron flux, and other important quantities as a function of burnup.
Attendees of this course will learn how to perform 2D depletion analyses using TRITON with the NEWT deterministic transport solver, with focus on applications relevant to light-water reactors (LWRs). The analysis of results will focus on mixture-specific power, burnup, and neutron flux, and the material inventory stored in ORIGEN nuclide concentration files (f71).
Participants will learn how to:
- Create the NEWT neutron transport model (material composition and the 2D geometry)
- Determine the input for power and use the power normalization options for depletion
- Perform branching calculations for few-group cross section generation
- Perform time-dependent perturbations of densities and temperatures
- Generate ORIGEN reactor libraries in support of rapid spent fuel characterization with SCALE’s ORIGAMI sequence
Application of SCALE’s Sampler sequence to perform uncertainty analysis for model parameters and nuclear data in TRITON simulations will be demonstrated.
No prior knowledge of SCALE is required.