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Glass strategy: Hanford’s enhanced waste glass program
The mission of the Department of Energy’s Office of River Protection (ORP) is to complete the safe cleanup of waste resulting from decades of nuclear weapons development. One of the most technologically challenging responsibilities is the safe disposition of approximately 56 million gallons of radioactive waste historically stored in 177 tanks at the Hanford Site in Washington state.
ORP has a clear incentive to reduce the overall mission duration and cost. One pathway is to develop and deploy innovative technical solutions that can advance baseline flow sheets toward higher efficiency operations while reducing identified risks without compromising safety. Vitrification is the baseline process that will convert both high-level and low-level radioactive waste at Hanford into a stable glass waste form for long-term storage and disposal.
Although vitrification is a mature technology, there are key areas where technology can further reduce operational risks, advance baseline processes to maximize waste throughput, and provide the underpinning to enhance operational flexibility; all steps in reducing mission duration and cost.
R. H. Iyer, H. Naik, A. K. Pandey, P. C. Kalsi, R. J. Singh, A. Ramaswami, A. G. C. Nair
Nuclear Science and Engineering | Volume 135 | Number 3 | July 2000 | Pages 227-245
Technical Paper | doi.org/10.13182/NSE00-A2136
Articles are hosted by Taylor and Francis Online.
The absolute fission yields of 46 fission products in 238U (99.9997 at.%), 46 fission products in 237Np, 27 fission products in 238Pu (99.21 at.%), 30 fission products in 240Pu (99.48 at.%), 30 fission products in 243Am (99.998 at.%), and 32 fission products in 244Cm (99.43 at.%) induced by fast neutrons were determined using a fission track-etch-cum-gamma spectrometric technique. In the case of highly alpha-active and sparingly available actinides - e.g., 238Pu, 240Pu, 243Am, and 244Cm - a novel recoil catcher technique to collect the fission products on a Lexan polycarbonate foil followed by gamma-ray spectrometry was developed during the course of this work. This completely removed interferences from (a) gamma rays of daughter products in secular equilibrium with the target nuclide (e.g., 243Am-239Np), (b) activation products of the catcher foil [e.g., 24Na from Al(n,)], and (c) activation products of the target [e.g., 238Np from 237Np(n,) and 239Np from 238U(n,)] reactions, making the gamma spectrometric analysis very simple and accurate. The high-yield asymmetric fission products were analyzed by direct gamma spectrometry, whereas the low-yield symmetric products (e.g., Ag, Cd, and Sb) as well as some of the asymmetric fission products (e.g., Br) and rare earths (in the case of 238U and 237Np) were radiochemically separated and then analyzed by gamma-ray spectrometry. The neutron spectra in the irradiation positions of the reactors were measured and delineated in the thermal to 10-MeV region using threshold activation detectors. The present data were compared with the ENDF/VI and UKFY2 evaluated data files. From the measured cumulative yields, the mass-chain yields have been deduced using charge distribution systematics. The mass yields, along with similar data for other fast neutron-induced fissioning systems, show several important features:1. Fine structure in the interval of five mass units in even-Z fissioning systems due to odd-even effects. The fine structure decreases from lighter to heavier even-Z actinides, in accordance with their odd-even effect.2. Higher yields in the mass regions 133 to 135, 138 to 140, and 143 to 145 and their complementary mass regions, depending on the mass of the fissioning systems due to the presence of 82n-66n, 86n-62n, and 88n-56n shells.3. For odd-Z fissioning systems having no odd-even effect, the fine structure is very feeble and is due only to shell effects.4. Unusually high yields observed in the mass region 133 to 139 in the fissioning system 239U* as compared to other U isotopes are explained on the basis of a higher neutron-to-proton ratio (N/Z) of 238U compared to lower-mass uranium isotopes. The [overbar], full-width at tenth-maximum, and [overbar]AL increase with increasing mass of the fissioning systems, whereas [overbar]AH of ~139 ± 1 remains constant throughout due to the strong preference for the formation of the deformed 88n shell, which is also favorable from the N/Z point of view.