Actinide Targets for Neutron Cross Section Measurements (C)
Description:
The Advanced Fuel Cycle Initiative (AFCI) and the Generation IV Reactor Initiative have demonstrated a lack of detailed neutron cross-sections for certain "minor" actinides, those other than the most common (235U, 238U, and 239Pu). For some closed-fuel-cycle reactor designs more than 50% of reactivity will, at some point, be derived from “minor” actinides that currently have poorly known (n,g) and (n,f) cross sections. A program of measurements under AFCI has begun to correct this. One …
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Date:
April 1, 2006
Creator:
Baker, J. D. & McGrath, C. A.
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Partner:
UNT Libraries Government Documents Department