Fine Temperature Grid Continuous Energy Cross Section Generation for Monte Carlo Analysis of Xe-100 Design
The standard “A Compact ENDF (ACE)” data libraries used by Monte Carlo based reactor physics codes calculations are provided by Los Alamos National Laboratory (LANL) with a temperature interval mostly of 300 K (e.g. 300 K, 600 K, 900 K) for the cross sections and between 100 K and 200 K for the thermal scattering […]
aLEU Fuel Trade Studies: Neutronics
The objective of the trade study presented in this report is to identify configurations for a water-cooled reactor system that satisfies a set of constraints. In this report we have illustrated the neutronics results for a trade study aiming at sorting among different choices in terms of geometries and components given a certain number of […]
Measurements of Effective Actinides Neutron Capture Cross-Sections in a Cadmium-Filtered Epithermal Neutron Spectrum
A total of 20 actinide samples were irradiated in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL): 233U (1), 235U (1), 236U (1), 238U (1), 237Np (2), 239Pu (1), 240Pu (1), 242Pu (2), 244Pu (2), 241Am (2), 243Am (2), 244Cm (2), and 248Cm (2). The samples were loaded in a basket containing a […]