Citation: G. Long, G. Gabrieli, M. Ruch, U. Steinitz, … [Read more...] about Simulation and Experimental Validation of the Effect of Neutron Absorbing Control Elements in Used Fuel on Advanced Experimental Fuel Counter Measurements
Stochastic And Data Uncertainty Quantificaiton Of MCNP Predicted Nuclide Concentrations In Fuel Burnup Simulations
Citation: S.N. Cerezo, S.S. Chirayath, G. Long, C. … [Read more...] about Stochastic And Data Uncertainty Quantificaiton Of MCNP Predicted Nuclide Concentrations In Fuel Burnup Simulations
A Comparison of Neutron Coincidence Rates Detected from Simulated Material Test Reactor Fuel Assemblies
Citation: G. Long, A. Trahan, M. Watson, M. Ruch, "A … [Read more...] about A Comparison of Neutron Coincidence Rates Detected from Simulated Material Test Reactor Fuel Assemblies
Uncertainty Quantification of Fission Product Concentration Estimation in MCNP Fuel Depletion Simulations
Citation:G.R. Long and S.S. Chirayath, "Uncertainty … [Read more...] about Uncertainty Quantification of Fission Product Concentration Estimation in MCNP Fuel Depletion Simulations
Nondestructive and destructive assay for forensics characterization of weapons-grade plutonium produced in LEU irradiated in a thermal neutron spectrum
Citation: S. Martinson, J. Garcia, I. Haynes, S. Saini, … [Read more...] about Nondestructive and destructive assay for forensics characterization of weapons-grade plutonium produced in LEU irradiated in a thermal neutron spectrum