b'(a) (b) (c)tion, thermal neutron radiography,Accomplishments: Figure 1. Schematic of the entire cask or acoustic methods. Ultimately, thisTo enable the aforementioned postwith motion control unit (a) and cross-development will provide pre- andirradiation characterization of bulksectional view to illustrate the beam path for incident and radiography post irradiation material characteriza- irradiated fuels, such as the AFC- neutron beams (b) (without motion tion that is not presently available2C/2D MOX fuels held back fromcontrol unit). The diameter of the cask which will benchmark simulationdestructive PIE for this purpose,is 15 inches and the lead layer in each codes and contribute to a solidshielding casks that allow to safelydirection of the sample is 10 cm. (c) Custom made aluminum sample holder scientific foundation for developmenthandle these fuels are required. Dosefor the irradiated 6mm diameter, 2 mm and licensing of nuclear fuels. Buildingrates of ~900R/hr are anticipated forthick U-10Zr-1Pd sample.these capabilities is part of the activitiesthese particular samples, imposing of a work package to develop advancedsubstantial demands on the cask post irradiation techniques. design. Therefore, the design of such 2020|AFC ACCOMPLISHMENTS 79'