A Novel Approach to Materials Development for Advanced Reactor Systems - Quarterly Progress Report: Year 2; Quarter 1

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

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

关键词: Alloys;    Irradiation;    Steels;    36 Materials Science;    Progress Report;   

DOI  :  10.2172/770633
RP-ID  :  NONE
RP-ID  :  FG03-99SF21927
RP-ID  :  770633

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 2; Quarter 1. There are three major goals for year two of the program. First, to build on the successful initial experiments on proton irradiation of pressure vessel steel to expand the irradiations to study dose rate and temperature effects, radiation effects on commercial alloys and to better characterize the precipitates. Second, we will begin irradiation and characterization of the Zircaloy alloys. Finally, we will continue low temperature irradiations and begin irradiation of chromium pre-enriched samples and cold-worked samples to assess the role of microstructure in IASCC of austenitic stainless steels. In quarter 1 of year 2, the project goal was to complete irradiation of model alloys of RPV steels for a range of doses and an initial sample characterization. We also planned to begin characterization of Zircalloy alloy samples and to make a set of cold-worked samples of 304 SS that would have a fixed hardness following subsequent irradiation to different doses.