Development of Molten Salt Reactor Modeling and Simulation Capabilities in VERA... Conference Paper September, 2019
Thermal and Neutronic Analysis for Irradiation of Advanced Neutron Absorbing Material in the High Flux Isotope Reactor Conference Paper September, 2019
Initial Accident Tolerant Fuel/Cladding Extensions to the VERA-to-Bison Offline Coupling Conference Paper September, 2019
Functionality Isolation Test for Fuel Cycle Code ORION - MOX Fuel Fabrication Conference Paper September, 2019
A Misload Analysis Methodology Supporting Criticality Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations Conference Paper September, 2019
Criticality Safety Analysis of Spent Nuclear Fuel Canisters Using As-Loaded Configurations Conference Paper September, 2019
Demonstration of MSR salt property database operation with a reactor analysis tool ORNL Report September, 2019
Initial Application of TSUNAMI for Validation of Advanced Fuel Systems Conference Paper September, 2019
