Actinide cross section data and inertial confinement fusion for long term waste disposal [electronic resource].

Published:: Livermore, Calif. : Lawrence Livermore Laboratory, 1979.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: Pages: 11 : digital, PDF file
Additional Creators:: Lawrence Livermore Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

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 tables required for Monte Carlo calculations of the burnup of /sup 241/Am and /sup 243/Am are discussed in connection with typical burnup reactor fusion and fission spectra. 2 figures.

Report Numbers:

E 1.99:ucrl-82177
E 1.99: conf-781174-6
conf-781174-6
ucrl-82177

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Note:

Published through SciTech Connect.
01/15/1979.
"ucrl-82177"
" conf-781174-6"
Conference on the nuclear data of higher plutonium and americium isotopes for reactor applications, Upton, NY, USA, 20 Nov 1978.
Meldner, H.

Funding Information:

W-7405-ENG-48

View MARC record | catkey: 14756093