FEASIBILITY STUDY OF DUPOLY TO RECYCLE DEPLETED URANIUM.
Description/Abstract
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.
| DOI | 10.2172/783829 |
|---|---|
| Creator/Author: | ADAMS,J.W. ; LAGERAAEN,P.R. ; KALB,P.D. ; RUTENKROGER,S.P. |
| Publication Date: | 1998 Feb 01 |
| OSTI Identifier: | OSTI ID: 783829 |
| Report Number(s): | BNL--52597; EW4010000 |
| DOE Contract Number: | AC02-98CH10886 |
| DOI: | 10.2172/783829 |
| Other Number(s): | R&D Project: 13470; Other: EW4010000; TRN: US0104096 |
| Resource Type: | Technical Report |
| Resource Relation: | Other Information: PBD: 1 Feb 1998 |
| Research Org: | Brookhaven National Lab., Upton, NY (US) |
| Sponsoring Org: | USDOE Office of Energy Research (ER) (US) |
| Subject: | 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 36 MATERIALS SCIENCE; DEPLETED URANIUM; ENCAPSULATION; POLYETHYLENES; URANIUM TETRAFLUORIDE; URANIUM TRIOXIDE; DENSITY; COMPRESSION STRENGTH; LEACHING; WASTE PRODUCT UTILIZATION |
| Country of Publication: | United States |
| Language: | English |
| Format: | Size: 20 pages |
| Update Date: | 2009 Jun 08 |
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