Using Ni-ion irradiation for the development of advanced materials for the next generation nuclear reactor
EMSL Project ID
2651
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
2002-11-01
End Date
2005-11-06
Status
Closed
Released Data Link
Team
Principal Investigator
Team Members