Disposition of nuclear waste using subcritical accelerator-driven systems [electronic resource].
- Washington, D.C. : United States. Dept. of Defense, 1998.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 9 pages : digital, PDF file
- Additional Creators:
- Los Alamos National Laboratory
United States. Department of Defense
United States. Department of Energy. Office of Scientific and Technical Information
- Studies have shown that the repository long-term radiological risk is from the long-lived transuranics and the fission products Tc-99 and I-129, thermal loading concerns arise mainly form the short-lived fission products Sr-90 and Cs-137. In relation to the disposition of nuclear waste, ATW is expected to accomplish the following: (1) destroy over 99.9% of the actinides; (2) destroy over 99.9% of the Tc and I; (3) separate Sr and Cs (short half-life isotopes); (4) separate uranium; (5) produce electricity. In the ATW concept, spent fuel would be shipped to a ATW site where the plutonium, other transuranics and selected long-lived fission products would be destroyed by fission or transmutation in their only pass through the facility. This approach contrasts with the present-day reprocessing practices in Europe and Japan, during which high purity plutonium is produced and used in the fabrication of fresh mixed-oxide fuel (MOX) that is shipped off-site for use in light water reactors.
- Published through SciTech Connect.
9. international conference on emerging nuclear energy systems (ICENES `98), Tel Aviv (Israel), 28 Jun - 2 Jul 1998.
Williamson, M.; Li, N.; Lawrence, G.; Houts, M.; Venneri, F.
- Funding Information:
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