publisher of
- Transitioning from Cobalt-60 to X-Ray or E-Beam for Medical Sterilization: Filling Data and Education Gaps. Transactions of the American Nuclear Society. 121:1089-1092. 2019
- Behavior of a Scaled Water-Cooled Reactor Cavity Cooling System under Hypothetical Accident Conditions. 1843-1846. 2020
- CFD Simulations on a hexagonal 61-pin wire-wrapped fuel bundle with STARCCM+ and comparison with experimental data.. 1509-1511. 2020
- Compatibility of 316H in Flowing Fluoride Salt at 550-650C. 470-471. 2020
- Design and Demonstration of a Rabbit Experiment System for the Versatile Test Reactor. 1408-1411. 2020
- Design and Optimization of the Shielding of an Accelerator Driven Thorium-Fueled Molten Salt Loop using MCNP6. 1259-1262. 2020
- Experimental investigation of cross-flow vortex structures in the wake region of a sphere using time-resolved PIV and POD analysis. 1847-1850. 2020
- Flow Rate Estimation from Transient Temperature Response of a Forced Convection Molten Salt Test Facility. 1863-1866. 2020
- Investigation of the Near Wake of a Sphere Using Time-Resolved Stereoscopic Particle Image Velocimetry. 1837-1840. 2020
- Lateral flow characterizations in a 5x5 rod bundle with spacer grid. 1689-1692. 2020
- Preparation of U-10Zr Alloys for Irradiation Testing in the Advanced Test Reactor to Enable MARMOT Assessment and Validation. 586-588. 2020
- Pressure Drop Measurements in a 61-Pin Wire Wrapped Hexagonal Fuel Bundle in Presence of Localized Subchannel Blockages. 1531-1534. 2020
- Subchannel Mass Transfer Analysis of a 5 x 5 Rod Bundle Using PIV and Matching of Index of Refraction. 1547-1549. 2020
- VALIDATION OF THE SAM STEADY-STATE MODEL OF THE FAST FLUX TEST FACILITY. 1654-1657. 2020
- Validation of Turbulence Models for Heat Transfer Predictions for Low-Pr Flows. 1497-1500. 2020
- Analysis of the VTR In-Core Environment with the Rabbit Delivery System Enabling Encapsulated Irradiations. 1427-1430. 2019
- Benchmark Exercise on Flow Mixing in Cold Leg of a Pressurized Water Reactor. 1783-1786. 2019
- Characterization of Nuclear Graphite for Molten Salt Reactors (MSR). 712-713. 2019
- Distributed Wall Temperature Measurements in a Scaled Water-Cooled RCCS. 183-186. 2019
- Experimental Investigation of Surrogate Particle Transport in a Turbulent Channel Flow: Versatile Test Reactor Program. 1153-1156. 2019
- Fast Responding Pressure Sensitive Paint Measurements in a Helical Coil Steam Generator Model. 1653-1656. 2019
- Gamma Source Imaging Using Non-Negative Least Squares. 1071-1074. 2019
- Non-Intrusive Velocity and Temperature Measurements of Buoyant Flows from Inductively Heated Dual-Spheres. 1633-1636. 2019
- Numerical Investigation of Fluid Flow in a Square ChannelVersatile Test Reactor Program. 1149-1152. 2019
- Reduced-Order Modeling of Fluid Flows in Closed-Loop Systems. 1762-1764. 2019
- Response Time of Thermowells for Corrosive, High-Temperature Experiments. 1673-1676. 2019