A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress Report, Year 1; Quarter 4

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

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

关键词: Hardening;    Ion Sources;    Alloys;    Irradiation;    36 Materials Science;   

DOI  :  10.2172/766527
RP-ID  :  None
RP-ID  :  FG03-99SF21927
RP-ID  :  766527

美国|英语

来源: UNT Digital Library

【 摘 要 】

OAK B188 A Novel Approach to Materials Development for Advanced Reactor Systems. Quarterly Progress Report, Year 1; Quarter 4. 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 chromium pre-enrichment and hardening by combining cold-work and irradiation 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 4, the project goal was to begin characterization of the microstructure of model alloys of RPV steels irradiated over a range of doses. We also planned to prepare samples for microstructure isolation in stainless steels, and to receive and characterize Zircaloy samples for subsequent irradiation.