NuScale will partner with Oak Ridge National Laboratory (ORNL) to perform a techno-economic analysis of a NuScale plant with a novel heat augmentation system for application to a commercial scale chemical production facility to help understand the functional requirements for the system and determine best ways to integrate with the facility.
This project will address first-of-a-kind (FOAK) experimental post-irradiation examination (PIE) of irradiation-induced bowing response in SiC-SiC structures.
Ultra has developed a prototype detector but to complete the anticipated testing program for the prototype detector and demonstrate suitable operation at reactor flux levels, the detector requires testing at fluxes equivalent to those typically seen in power reactor operation (1E10 – 1E11nv).
This workshop will focus on multiple topics, including overviews of US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) MSR released activities and overviews of the US DOE Office of Nuclear Energy (NE) MSR technology development and advanced modeling and simulation activities.
The project will evaluate the criticality safety limits of the conceptual equipment designs for NuCycle™.
Elementl is evaluating dozens of locations in the U.S. for siting suitability of advanced reactor technologies.
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 2021 Molten Salt Reactor Workshop was held virtually on October 12-13, 2021 from Oak Ridge National Laboratory. There was a tremendous response to the workshop this year and approximately 700 people registered for the event.
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.