Savannah River National Laboratory (SRNL) will provide the requisite expertise and spent fuel handling capability to enable the laboratory scale assessment and demonstration. The data generated at laboratory scale would provide confirmation of feasibility and basis for scaling to an industrial scale capability.
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.
The objective of this project is to close the gap in the detection and quantification of radiation aging and combined thermal and radiation aging in nuclear cable applications using electrical test methods.
Vega Wave Systems has developed a camera head and needs to complete radiation testing to achieve market acceptance and verify radiation tolerance limits.
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.
Neutroelectric and Oak Ridge National Laboratory will perform critical combined tests at the High Flux Isotope Reactor in support of qualification of this new material, NE-300, for use in commercial nuclear reactor applications.
Westinghouse Electric Company and Oak Ridge National Laboratory designed and performed an experiment to develop a non-destructive assay measurement method that addressed the challenges of the volumetric deposits within the large ventilation system housings.
Framatome used failure modes and effects analysis (FMEA) to determine and define potential failure mechanisms for the U-50Zr alloy design.
The objective of this project was to improve nuclear power generation’s safety and competitiveness by providing robust information about the flow patterns and formations throughout the simulated fluid domain.
The objective of this project was to determine if currently available technology can be used to modernize the PSP to a level of cost-effectiveness to realize the potential cost saving in the nuclear fuel cycle.