Publications

Apr, 2026

Journal

Computational Thermal Hydraulics of a High-Performance Low-Enriched-Uranium Annular Target for HFIR Irradiation

Molybdenum-99 has been historically generated via isolation from fission products of fissioned highly enriched uranium targets. The isotope is of significant demand due to its daily use across the planet in radiopharmaceutical medical procedures. The primary objective of this paper was to design and analyze an experimental target assembly containing one low enriched uraniu…

Mar, 2026

Conference Paper

Estimating Heat Generation and Energy Deposition in Low-Enriched Uranium Foil Targets

Mar, 2026

Conference Paper

Application of the Monte Carlo Method with ORIGEN for Salt Sample Analysis in INL’s Advanced Test Reactor Test Beds

Mar, 2026

Conference Paper

Molten Salt Species Solubility Calculations Using Thermochimica’s Gibbs Energy Minimizer (GEM)

Mar, 2026

Conference Paper

Xenon Gas and Liquid Phase Concentrations with/without Off-System in the Iodine Liquid of the MSRE Loop

Nov, 2024

ORNL Report

Bubble mass transport measurement in the large-scale tests loops at Oak Ridge National Laboratory

Jul, 2024

ORNL Report

Behavior of contaminants and simulant fission products in the advanced chlorination process

Jun, 2024

Journal

Semi-empirical model for Henry’s law constant of noble gases in molten salts

Henry’s law constant, which describes the proportionality of dissolved gas to partial pressure of free gas in liquid–gas equilibrium systems, can also be applied to mass transport applications. In this work, we investigated an approach for determining the solubility of noble gases in a molten salt liquid utilizing the equilibrium concept of Henry’s gas constant. Henry’s ga…

May, 2024

Conference Paper

Transport of Highly Volatile Gases Related to Noble Gases and Tritium in the MSRE

This study aims to comprehend mass transfer in the closed-loop circulation of highly volatile gases, including noble gases and tritium. We explore the impact of steady-state xenon-135 and tritium on the MSRE and reveal their isotopic distributions using online noble gas stripping of fuel salts. The MSRE was engineered to extract fission product gases from fuel salts and ef…

Feb, 2024

Journal

Coupled neutronics and species transport simulation of the Molten Salt Reactor Experiment

This paper presents the development of coupling between the molten salt reactor species transport code Mole and the reactor physics code Griffin. In this study, tracking of delayed neutron precursors was investigated in the Molten-Salt Reactor Experiment (MSRE), accounting for changes in fuel flow velocity as a function of position in the primary loop. The neutron transpor…

Dec, 2023

Conference Paper

Engineering Scale Simulation of Ortho- Para Hydrogen Conversion Using Hydrogen Analysis Runtime Environment (Hare) in the MOOSE Framework

Dec, 2023

Conference Paper

Multiphysics Mass Accountancy Calculation for Noble Metals Tracking in MSRE Loop