2017 | AFC ACCOMPLISHMENTS 160 The Fuel Cycle Research and Development (FCRD) program is investigating options to transmute minor actinides.To achieve this goal, new fuels and cladding materials must be developed and tested to high burnup levels (e.g. >20%) requiring cladding to withstand very high doses (greater than 200 dpa) while in contact with the coolant and the fuel. Project Description: To develop and qualify materials to a total fluence greater than 200 dpa requires development and testing of advanced alloys and irradiations in fast reactors. Specimens of previously irradiated HT9 specimens are being irradiated in a fast reactor to high doses (>200 dpa). In addition, improvements in the radiation tolerance of HT-9 are being made through minor changes in the composition.Advanced radiation tolerant materials with fine oxide dispersion strengthening are also 3.3 AR CORE MATERIALS ODS Tube and Rod Process Development Principal Investigator: Stuart Maloy Collaborators: Eda Aydogan (LANL), Dave Hoelzer/ORNL, Curt Lavender/PNNL, Bob Odette/UCSB, John Lewandowski/CWRU Figure 1. Analysis of oxide particles in 14YWT using Atom Probe Tomography after irradiation with Fe ions to extreme doses show excellent stability even to the highest dose of 585 dpa. (Aydogan, E., Almirall, N., Odette, G.R., Maloy, S.A., Anderoglu, O., Shao, L., Gigax, J.G., Price, L., Chen, D., Chen, T., Garner, F.A., Wu, Y., Wells, P., Lewandowski, J.J., Hoelzer, D.T).