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Inertial Confinement Fusion and Long-Term Nuclear Waste Management

Heiner Meldner

Nuclear Science and Engineering / Volume 69 / Number 3 / March 1979 / Pages 438-441

Technical Note / dx.doi.org/10.13182/NSE79-A19963

Inertial confinement fusion (ICF) pellet center burnup of fission reactor waste, namely, 14-MeV neutron fission of the very long-lived actinides that pose storage problems, is calculated for realistic target designs. A major advantage of pellet center burnup is safety: Only milligram quantities of highly toxic and active material need to be present in the fusion chamber, whereas blanket burnup reqUires the continued presence of tons of actinides in a small volume. One ICP plant can transmute the actinide waste of up to ten power equivalent fission reactors, i.e., large-scale development appears to provide a foreseeable-future technology that greatly reduces the necessity of high integrity waste storage (burial) time: from 107 to just over 102 yr.