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2014 ANNUAL REPORT 89 Figure 1. Irradiation- induced dislocation loop diameter and number density produced by proton and neutron irradiations to 3 dpa at 500C in HCM12A and HT9. Project Description The goal of this project is to better understand the effects of varying dose rates on F-M alloys by comparing the damage inflicted on two identically heated commercial alloys HCM12A and HT9 by neutron and proton irradiation. Both alloys were irradiated in the ATR with neutrons at a dose rate of 10-7 dpasec and with 2.0 MeV protons at 10-5 dpasec. Both irradiations were carried out to 3 dpa at a temperature of 500C. Because it aims to 1 understand the response of advanced reactor candidate structural materials to irradiation and 2 assess the ability of proton irradia- tions to emulate in-reactor neutron irradiation damage this project has direct relevance to the Advanced ReactorTechnologies program being conducted by the Department of Energys Office of Nuclear Energy DOE-NE. The primary DOE-NE mission is to advance nuclear power as a viable resource for meeting the nations energy environmental and national security needs. Generation IV advanced reactor designs such as high- temperature reactors and fast-neutron spectrum reactors fulfill this mission by combining high-efficiency power generation with the environmental and national security benefits of consuming the extended-life radioactive isotopes found in spent nuclear fuel. However along with the promise of Generation IV designs comes the challenge of finding suitable structural This project enabled two graduate students to develop proficiency in microscopy techniquesand has laid the groundwork for their thesis projects. JanelleWharryAssistant ProfessorMaterials Science EngineeringBoise State University