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M A T E R I A L S T E S T I N G / C H A R A C T E R I Z A T I O N
Samuel A. Briggs* and Kumar Sridharan, FASM,*
University of Wisconsin, Madison
Kevin G. Field, Oak Ridge National Laboratory, Tenn.
*Member of ASM International
Development of new, radiation-tolerant
materials that maintain the structural
integrity and safety margins over the course
of a nuclear power reactor’s service life
requires the ability to predict degradation
phenomena.
CORRELATIVE MICROSCOPY
OF NEUTRON-IRRADIATED
MATERIALS