Nuclear Technology

Analysis of Core Characterization Transients for TREAT Restart

Development of an Experimental Routine for Electrochemical and Laser-Induced Breakdown Spectroscopy Composition Measurements of SmCl3 in LiCl-KCl Eutectic Salt Systems

Using Kernel Density Estimation to Detect Loss-of-Coolant Accidents in a Pressurized Water Reactor

Dynamic Modeling and Performance Analysis of a Two-Fluid Molten-Salt Breeder Reactor System

Response Matrix Method-Based Importance Solver and Variance Reduction Scheme in the Serpent 2 Monte Carlo Code

Development of the Tritium Transport Analysis Code for the Thorium-Based Molten Salt Reactor

Verification of Modelica-Based Models with Analytical Solutions for Tritium Diffusion

ATR Compendium: Irradiation Test Capabilities

Tritium Transport Analysis in a 2-MW Liquid-Fueled Molten Salt Experimental Reactor with the Code TMSR-TTAC

Ab-Initio Calculation of Spectral Absorption Coefficients in Molten Fluoride Salts with Metal Impurities