FEASIBILITY STUDY OF DUPOLY TO RECYCLE DEPLETED URANIUM.

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DUPoly, depleted uranium (DU) powder microencapsulated in a low-density polyethylene binder, has been demonstrated as an innovative and efficient recycle product, a very durable high density material with significant commercial appeal. DUPoly was successfully prepared using uranium tetrafluoride (UF{sub 4}) ''green salt'' obtained from Fluor Daniel-Fernald, a U.S. Department of Energy reprocessing facility near Cincinnati, Ohio. Samples containing up to 90 wt% UF{sub 4} were produced using a single screw plastics extruder, with sample densities of up to 3.97 {+-} 0.08 g/cm{sup 3} measured. Compressive strength of as-prepared samples (50-90 wt% UF4 ) ranged from 1682 {+-} 116 psi (11.6 ... continued below

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20 pages

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ADAMS,J.W.; LAGERAAEN,P.R.; KALB,P.D. & RUTENKROGER,S.P. February 1, 1998.

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DUPoly, depleted uranium (DU) powder microencapsulated in a low-density polyethylene binder, has been demonstrated as an innovative and efficient recycle product, a very durable high density material with significant commercial appeal. DUPoly was successfully prepared using uranium tetrafluoride (UF{sub 4}) ''green salt'' obtained from Fluor Daniel-Fernald, a U.S. Department of Energy reprocessing facility near Cincinnati, Ohio. Samples containing up to 90 wt% UF{sub 4} were produced using a single screw plastics extruder, with sample densities of up to 3.97 {+-} 0.08 g/cm{sup 3} measured. Compressive strength of as-prepared samples (50-90 wt% UF4 ) ranged from 1682 {+-} 116 psi (11.6 {+-} 0.8 MPa) to 3145 {+-} 57 psi (21.7 {+-} 0.4 MPa). Water immersion testing for a period of 90 days produced no visible degradation of the samples. Leach rates were low, ranging from 0.02 % (2.74 x 10{sup {minus}6} gm/gm/d) for 50 wt% UF{sub 4} samples to 0.72 % (7.98 x 10{sup {minus}5} gm/gm/d) for 90 wt% samples. Sample strength was not compromised by water immersion. DUPoly samples containing uranium trioxide (UO{sub 3}), a DU reprocessing byproduct material stockpiled at the Savannah River Site, were gamma irradiated to 1 x 10{sup 9} rad with no visible deterioration. Compressive strength increased significantly, however: up to 200% for samples with 90 wt% UO{sub 3}. Correspondingly, percent deformation (strain) at failure was decreased for all samples. Gamma attenuation data on UO{sub 3} DUPoly samples yielded mass attenuation coefficients greater than those for lead. Neutron removal coefficients were calculated and shown to correlate well with wt% of DU. Unlike gamma attenuation, both hydrogenous and nonhydrogenous materials interact to attenuate neutrons.

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20 pages

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  • Other Information: PBD: 1 Feb 1998

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  • Report No.: BNL--52597
  • Report No.: EW4010000
  • Grant Number: AC02-98CH10886
  • DOI: 10.2172/783829 | External Link
  • Office of Scientific & Technical Information Report Number: 783829
  • Archival Resource Key: ark:/67531/metadc717373

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Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 1, 1998

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  • Sept. 29, 2015, 5:31 a.m.

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  • Nov. 9, 2015, 12:08 p.m.

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ADAMS,J.W.; LAGERAAEN,P.R.; KALB,P.D. & RUTENKROGER,S.P. FEASIBILITY STUDY OF DUPOLY TO RECYCLE DEPLETED URANIUM., report, February 1, 1998; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc717373/: accessed April 23, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.