Planning for the Management and Disposition of Newly Generated TRU Waste from REDC Page: 3 of 13
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WM'02 Conference, February 24-28, 2002, Tucson, AZ
The Transuranium Element Processing Program supplies critical isotopes for research activities
to both the DOE weapons laboratories and the multi-program research, design, and development
(RD&D) laboratories. Isotopes produced under this program include Am-243, Bk-249, Cf-249,
Cf-252, Cm-244, Cm-248, Es-253, Es-254, Fm-255, and Fm-257, as well as various fission
products. The Mark-42 Program recovers transuranic (TRU) elements, including Am-243, Cm-
244, and Pu-242, from reactor targets.
The Californium-252 Industrial Sales/Loan Program provides Cf-252 neutron sources to more
than 70 institutions (2). These institutions consist of DOE or integrated contractors; U.S.
Government agencies, including military installations, educational and medical institutions; and
private research organizations. The uses of these sources include medical research or treatment,
classroom instruction or demonstration, and R&D or industrial applications (e.g., reactor startup,
radiography, neutron activation analysis, and explosives detection). Specific defense/military
uses of the Cf-252 neutron sources include the following:
" Nondestructive inspection of explosive fill in detonators at Mound;
" Neutron activation analysis at the Savannah River Site (SRS);
" Assay of high-level glass at the Hanford Site;
" Nondestructive assay systems for fissile and TRU wastes at Los Alamos National Laboratory
(LANL) and the Idaho National Engineering and Environmental Laboratory (INNEL); and
" Neutron radiography to locate corrosion on military fighter aircraft at McClellan Air Force
Generator/storage sites must demonstrate that their waste is not spent nuclear fuel or high-level
waste as defined in the Waste Isolation Pilot Plant Land Withdrawal Act. Spent nuclear fuel is
fuel that has been removed from a reactor but has not undergone reprocessing. The hot cell waste
consists of miscellaneous debris from isotope recovery and purification, not spent nuclear fuel.
Although irradiated actinide targets are processed for isotope recovery, they do not end up in the
waste. Therefore, TRU waste generated from the isotope recovery/production operations at the
Building 7920 and 7930 hot cells is eligible for disposal at Waste Isolation Pilot Plant (WIPP). It
is generated in whole or in part from the following defense activities: naval reactors development
(as a substitute naval reactor), verification and control technology, defense nuclear waste and
materials by-products management, and defense research and development. The waste also does
not meet the definition of either spent nuclear fuel or high-level waste as provided in the Waste
Isolation Pilot Plant Land Withdrawal Act.
TRU waste is generated at the REDC in the hot cells of Buildings 7920 and 7930 (1) and in the
support laboratories. The Building 7920 hot cells are used for four activities: target fabrication
(cells 1-3), transuranium element processing (cells 4-7), analytical sample collection/storage (cell
8), and waste handling (cell 9). The layout of the Building 7920 hot cells is shown in Figure 2.
The target fabrication consists of a series of mechanical operations to produce actinide targets for
irradiation in the High Flux Isotope Reactor (HFIR) located at REDC. A number of quality
assurance inspections are performed as part of target fabrication.
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Coffey, D. E.; Forrester, T. W. & Krause, T. Planning for the Management and Disposition of Newly Generated TRU Waste from REDC, article, February 26, 2002; Tucson, Arizona. (digital.library.unt.edu/ark:/67531/metadc785577/m1/3/: accessed September 24, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.