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Radionuclide Leaching from Residual Solids Remaining after Acid Dissolution of Composite K East Canister Sludge

Description: Laboratory tests were performed to examine mixed nitric/hydrofluoric acid leach treatments for decontaminating dissolver residual solids (KECDVSR24H-2) produced during a 20- to 24-hr dissolution of a composite K East (KE) Basin canister sludge in 95 C 6 M nitric acid (HNO{sub 3}). The scope of this testing has been described in Section 4.5 of ''Testing Strategy to Support the Development of K Basin Sludge Treatment Process'' (Flament 1998). Radionuclides sorbed or associated with the residual solids generated in the K Basin sludge treatment process can restrict disposal of this solid to the Environmental Restoration Disposal Facility (ERDF). The starting dissolver residual solid for this testing, KECDVSR24H-2, contains radionuclides at concentrations which exceed the ERDF Waste Acceptance Criteria for TRU by about a factor of 70, for {sup 239}Pu by a factor of 200, and for {sup 241}Am by a factor of 50. The solids also exceed the ERDF criterion for {sup 137}Cs by a factor of 2 and uranium by a factor of 5. Therefore, the radionuclides of greatest interest in this leaching study are first {sup 239}Pu and {sup 241}Am (both components of TRU) and then uranium and {sup 137}Cs.
Date: April 2, 1999
Creator: Delegard, C.H.; Rinehart, D.E.; Soderquist, C.Z. & Fadeff, S.K.
Partner: UNT Libraries Government Documents Department

Radionuclide Leaching from Residual Solids Remaining after Acid Dissolution of K East Area Sludge Composite

Description: Laboratory tests were performed to examine the efficacy of various leach treatments for decontaminating dissolver residual solids (KEACRESID1) produced during a 24-hour dissolution of K East Basin floor and Weasel Pit sludge composite in boiling 6 M HNO{sub 3}. The scope of this testing has been described in Section 4.5 of ''Testing Strategy to Support the Development of K Basin Sludge Treatment Process'' (Flament 1998). Radionuclides sorbed or associated with the residual solids generated in the K Basin sludge treatment process can restrict disposal of this solid to the Environmental Restoration Disposal Facility (ERDF). The starting dissolver residual solid for this testing, KEACRESID1, is a visibly heterogeneous material. This material contains radionuclides at concentrations above the ERDF Waste Acceptance Criteria for transuranics (TRU) by about a factor of 3, for {sup 239}Pu by a factor of 10, and for {sup 241}Am by a factor of 1.6. It meets the ERDF criterion for {sup 137}Cs by a factor of 4 and for uranium by a factor of 10. Therefore, the radionuclides of greatest interest in this leaching study are first {sup 239}Pu, and then {sup 241}Am, {sup 137}Cs, and uranium.
Date: April 2, 1999
Creator: Delegard, C.H.; Rinehart, D.E.; Carlson, C.D.; Soderquist, C.Z. & Fadeff, S.K.
Partner: UNT Libraries Government Documents Department

Inorganic and Radiochemical Analysis of AW-101 and AN-107 ''Diluted Feed'' Materials

Description: This report presents the inorganic and radiochemical analytical results for AW-101 and AN-107 diluted feed materials. The analyses were conducted in support of the BNFL Proposal No. 29952/29953 Task 2.1. The inorganic and radiochemical analysis results obtained from the diluted feed materials are used to provide initial characterization information for subsequent processing testing. Quality Assurance (QA) Plan MCS-033 provides the operational and quality control protocols for the analytical activities.
Date: November 11, 1999
Creator: Urie, M. W.; Wagner, J. J.; Greenwood, L. R.; Farmer, O. T.; Fiskum, S. K.; Ratner, R. T. et al.
Partner: UNT Libraries Government Documents Department

Inorganic, Radioisotopic, and Organic Analysis of 241-AP-101 Tank Waste

Description: Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids.
Date: October 17, 2000
Creator: Fiskum, S.K.; Bredt, P.R.; Campbell, J.A.; Farmer, O.T.; Greenwood, L.R.; Hoppe, E.W. et al.
Partner: UNT Libraries Government Documents Department

C-106 High-Level Waste Solids: Washing/Leaching and Solubility Versus Temperature Studies

Description: This report describes the results of a test conducted by Battelle to assess the effects of inhibited water washing and caustic leaching on the composition of the Hanford tank C-106 high-level waste (HLW) solids. The objective of this work was to determine the composition of the C-106 solids remaining after washing with 0.01M NaOH or leaching with 3M NaOH. Another objective of this test was to determine the solubility of various C-106 components as a function of temperature. The work was conducted according to test plan BNFL-TP-29953-8,Rev. 0, Determination of the Solubility of HLW Sludge Solids. The test went according to plan, with only minor deviations from the test plan. The deviations from the test plan are discussed in the experimental section.
Date: January 26, 2000
Creator: Lumetta, G. J.; Bates, D. J.; Berry, P. K.; Bramson, J. P.; Darnell, L. P.; Farmer, O. T., III et al.
Partner: UNT Libraries Government Documents Department