Transient Overpower Testing in THOR -- Pre-Test PIE of Previously Irradiated Fuel and NDE PIE Results of Commissioning Test
Presentation for AFC Meeting on PIE Results for THOR Capsule Over Power Testing
Engineering topics
Publications and source records attributed to Turner, Clayton G.
Presentation for AFC Meeting on PIE Results for THOR Capsule Over Power Testing
Initial planning for performing quantitative analysis on LOCA tested specimens
Follow-on experimentation of irradiated nuclear fuel is critical to understanding fuel behavior at different stages of the fuel lifecycle. Transient experiments using fuel with high burnup can enlarge understanding of fuel fragmentation, relocation and dispersal under various reactor accident situations. Assembling experiments with such fuel requires remote operations.
Heat pipes are highly effective devices used to passively transport heat by two-phase capillary action. Their small footprint, light weight and lack of moving parts make them ideal for transportable nuclear microreactors, where size and weight are limited, minimal to no operation and maintenance are required, and high reliability is desired. The use of additive manufacturing allows for the fabrication of heat pipes with performance enhancements, such as microchannels, grooves, arteries, or tailored porosity, which are difficult, expensive or impossible to achieve with traditional fabrication techniques. We are evaluating the capabilities of the Admaflex 130 Digital Light Printer to produce these geometries by characterizing feature shrinkage, developing an optimal heat treatment recipe, assessing the effects of heat treatment atmosphere and varying print orientation. Computational simulations are being used to estimate performance of the various 3D printed configurations.