Search Results

Advanced search parameters have been applied.
open access

Actinide cross section data and inertial confinement fusion for long term waste disposal

Description: Actinide cross section data at thermonuclear neutron energies are needed for the calculation of ICF pellet center burnup of fission reactor waste, viz. 14 MeV neutron fission of the very long-lived actinides that pose storage problems. A major advantage of pellet center burnup is safety: only milligrams 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. The actinide data tab… more
Date: January 15, 1979
Creator: Meldner, Heiner
Partner: UNT Libraries Government Documents Department
Back to Top of Screen