The standard review plans for storage of spent nuclear fuel and transportation of fissile
materials do not address, in detail, the technical considerations for crediting the neutron
absorber content of metal matrix composites used for preventing nuclear criticality. The Division
of Spent Fuel Storage and Transportation (SFST) considers the application of acceptance
criteria and methodology described in the recently developed American Standard for Testing
and Materials (ASTM) standard practice C1671-07, “Standard Practice for Qualification and