A Novel Approach to Material Development for Advanced Reactor Systems

Was, G.S. ; Atzmon, M. ; Wang, L.

University of Michigan, Ann Arbor, MI (United States)

关键词: Ion Sources;    Alloys;    Irradiation;    36 Materials Science;    Stainless Steels;   

DOI  :  10.2172/761592
RP-ID  :  None
RP-ID  :  FG03-99SF21927
RP-ID  :  761592

美国|英语

来源: UNT Digital Library

【 摘 要 】

OAK B188 A Novel Approach to Material Development for Advanced Reactor Systems. Year one of this project had three major goals. First, to specify, order and install a new high current ion source for more rapid and stable proton irradiation. Second, to assess the use of low temperature irradiation and chromium pre-enrichment in an effort to isolate a radiation damage microstructure in stainless steel without the effects of RIS. Third, to initiate irradiation of reactor pressure vessel steel and Zircaloy. In year 1 quarter 3, the project goal was to complete irradiation of model alloys of RPV steels for a range of doses and begin sample characterization. We also planned to prepare samples for microstructure isolation in stainless steels, and to identify sources of Zircaloy for irradiation and characterization.