▶ Date: 2024. 05. 03(Fri)

▶ Time: 10:00 ~ 11:00AM

▶ Venue: Research Building I, #310

▶ Speaker: Dr. Byoung-kyu Jeon(Oak Ridge National Laboratory)

▶ Title: Overview of SCALE and ORIGEN in Nuclear Energy

▶ Abstract: The SCALE code system is a widely used modeling and simulation suite for nuclear safety analysis and design that is developed, maintained, tested, and managed by the Oak Ridge National Laboratory. SCALE provides a comprehensive, verified and validated, user-friendly tool set for criticality safety, reactor physics, radiation shielding, radioactive source term characterization, and sensitivity and uncertainty analysis. Since 1980, regulators, licensees, and research institutions around the world have used SCALE for safety analysis and design. SCALE provides an integrated framework with dozens of computational modules, including three deterministic solvers, three Monte Carlo radiation transport solvers and one depletion solver selected based on the user’s desired solution strategy. The Oak Ridge Isotope Generation (ORIGEN) code in SCALE calculates time-dependent concentrations, activities, and radiation source terms for a large number of isotopes simultaneously generated or depleted by neutron transmutation, fission, and radioactive decay. Provisions are made to include continuous nuclide feed rates and continuous chemical removal rates that can be described with rate constants for application to reprocessing or other systems that involve nuclide removal or feed. Within SCALE, transport codes can be used to model user-defined systems, and the ORIGEN code can calculate problem-dependent neutron-spectrum-weighted cross sections representative of conditions within any given reactor or fuel assembly and then convert these cross sections into a library to be used by ORIGEN.