A Novel Approach to Material Development for Advanced Reactor Systems | Zendy

Gary S. Was | Zendy; M. Atzmon | Zendy; L. Wang | Zendy

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A Novel Approach to Material Development for Advanced Reactor Systems

Author(s) -

Gary S. Was,

M. Atzmon,

L. Wang

Publication year - 2000

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/761592

Subject(s) - irradiation , microstructure , materials science , reactor pressure vessel , metallurgy , chromium , nuclear engineering , proton , radiochemistry , chemistry , engineering , nuclear physics , physics

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

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