Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor
EMSL Project ID
2651a
Abstract
Objective__To evaluate the radiation response of different alloy system for the microstructural and microchemical analysis. Approach__Using Ni-ion irradiation at T=500C to doses up to 150 dpa for austenitic and ferritic/martensitic stainless steels and alloys modified with over-sized solute addition to explore the radiation resistant alloys applicable for the cores of next generation nuclear reactors. Specific Instruement Needed__Tandem Accelerator at EMSL.
Project Details
Project type
Exploratory Research
Start Date
2005-11-01
End Date
2007-01-11
Status
Closed
Released Data Link
Team
Principal Investigator
Team Members
Related Publications
T. R. Allen, J. Gan, J. I. Cole, M. K. Miller, J. T. Busby, S. Shutthanandan and S. Thevuthasan, “Radiation Response of a 9 Cr Oxide Dispersion Strengthened ODS to Heavy Ion Irradiation,” J. Nucl. Mater., 375 (2008) 26.