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

Technical Report ·
DOI:https://doi.org/10.2172/770633· OSTI ID:770633

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.

Research Organization:
University of Michigan, Ann Arbor, MI (US)
Sponsoring Organization:
US Department of Energy (US)
DOE Contract Number:
FG03-99SF21927
OSTI ID:
770633
Resource Relation:
Other Information: PBD: 25 Jun 2002
Country of Publication:
United States
Language:
English