AFIP-7 Post-irradiation Examination Summary Report
The following report contains the results and conclusions from post irradiation examinations performed on the fuel plates irradiated as part of the AFIP-7 experiment, the first test of base monolithic fuel in a fuel assembly consisting of curved, constrained fuel plates. These examinations include visual examination; eddy-current testing to measure oxide growth; profilometry to measure […]
Uranium-zirconium hydride nuclear fuel performance in the NaK-cooled MARVEL microreactor
The Microreactor Applications Research Validation and EvaLuation (MARVEL) Project is producing a high temperature NaK-cooled nuclear reactor test bed at the Idaho National Laboratory to ultimately improve integration of microreactors to end-user applications. This ambitious effort seeks to design, authorize, construct, test, and operate the reactor within five years. The computational software package chosen for […]
Post irradiation examination of a uranium-zirconium hydride TRIGA fuel element
Low-enriched (LEU) U-ZrH fuel, with a235U content less than 20% of the total uranium, is being evaluated for possible use in different types of reactors, including space nuclear systems, light water reactors (LWRs) and micro-reactors. As a result, it is beneficial to better understand the macrostructural and microstructural changes that occur in this fuel during […]