TVA has begun planning an Advanced Nuclear Program and is beginning to study future deployment of advanced nuclear reactors (ANRs). This project will screen the TVA service area to help determine suitable sites for future ANR deployment.
Previous studies for UF6 limits in shipping containers were limited to enrichment up to 5%. The objectives of this new study will take that enrichment to 10%. The project will review the available literature and update these studies with current techniques, evaluate the impact of higher enrichments in safety criticality cases in transport conditions, and publish a report that will serve as the basis to the safety criticality analysis that will be provided for review and approval to the radioactive material transport regulators, for the DN-30 package with 30B cylinders containing enrichment higher than 5%.
The objective of this project is to evaluate a metalorganic framework (MOF) for continuous separation of Xe and Kr from the off-gas in the FCMSR in order to optimize the noble gas management of the FC-MSR and chemical processes for fuel salt production and conditioning and support the safety and licensing bases.
Westinghouse and Oak Ridge National Laboratory will use multiphysics design optimization methods and additive manufacturing to help develop new nuclear components as well as optimized replacements to existing components that are optimum for meeting design requirements and are manufacturable.
The objective of this project is to explore a number of advanced heterogenous fuel design concepts to improve the operational, safety, and economic performance of existing power plants.
The 2020 Molten Salt Reactor Workshop was held virtually on October 14–15, 2020 from Oak Ridge National Laboratory. There was an overwhelming response to the workshop this year and approximately 500 people registered for this year’s workshop.
The objective of this project was to analyze reactor core and system behavior in response to anticipated transients and accident scenarios and to use the Virtual Environment for Reactor Applications (VERA) code suite, which employs multi-physics simulation to model feedback behavior in the reactor core.
The objective of this project is to develop Terrestrial Energy USA’s high temperature gamma thermometer (HTGT) that will accurately determine IMSR® power levels under all normal and off-normal reactor operating conditions. The HTGT will ensure safe and effective control of IMSR® reactor-core power and will be applicable to other MSR designs.
The objective of this project is to characterize Urbix Resources’ purified graphite powder, fabricate solid specimens of graphite matrix material, and conduct post-fabrication testing for properties determination. By decreasing feedstock cost, production time, and environmental impact, Urbix Resources expects to achieve competitive nuclear graphite grades at a discounted price.
The objective of this project is to quantify the economic advantages of burning spent nuclear fuel (SNF) from light water reactors (LWRs) in a GEM*STAR accelerator-driven subcritical reactor.