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2014 ANNUAL REPORT 141 profiles of the irradiated specimens from Capsules A and B were then measured and the results analyzed to determine the average growth strain of each specimen. In addition to strain measurements other objectives included performing as-run reactor physics analysis to determine dpa measuring neutron fluence using flux wires installed in the experiment performing heat transfer calculations to determine irradiation temperature and obtaining temperature indica- tions from monitors melt wires and silicon-carbide installed in the experiment.These objectives have also been completed for Capsules A and B. Future Activities The growth strain data at 6.7 dpa CapsuleA and 12.3 dpa Capsule B are being evaluated in 2015 to ascertain the effects of neutron fluence alloy composition and H content on growth strain.The results will be given to the Electric Power Research Institute EPRI and shared with private-sector fuel suppliers AREVA Global Nuclear Fuels andWestinghouse that provided some of the Zr alloys used in this experiment. TEM will be used to analyze selected irradiated specimens to study the mech- anism of irradiation growth. Procedures for preparing specimens forTEM analysis are currently being developed at the irradiated materials characterization facilities at INL and include electro- polishing and ion-polishing. Moreover this project will continue to develop the research capability and staffing required to meet industry needs for research and development of nuclear materials. Publications and Presentations 1. P. E. Murray J. R. Parry J. H. Jackson 2014 Interim Report on CapsuleA of the ZirconiumAlloy Irradiation Growth Experi- ment in theAdvancedTest Reactor. INLLTD 14 31110 Rev. 1 June 2014. 2. P. E. Murray J. R. Parry J. Navarro 2014 Interim Report on Capsule B of the ZirconiumAlloy Irradiation Growth Experi- ment in theAdvancedTest Reactor. INLLTD 14 33859 December 2014. See additional publications from other years in the Media Library on the NSUF website. This project demonstrates that the nuclear industry can benefit from INLs capability in nuclear materials testing. Dr.Paul MurrayINL Distributed Partnership at a Glance ATR NSUF and Partners Facilities and Capabilities Idaho National Laboratory AdvancedTest Reactor Hot Fuels Examination Facility Center for Advanced Energy Studies Microscopy and Characterization Suite Collaborators Idaho National Laboratory Paul Murray principal investigator Electric Power Research Institute SureshYagnik collaborator