Radionuclide Leaching from Organic Ion Exchange Resin

Delegard, Calvin H.; Rinehart, Donald E.

doi:10.2172/5106

Cited by 3 publications

(9 citation statements)

References 3 publications

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“…The two-step nitric/oxalic acid treatment generally gave better overall solids decontamination than the Ce(IV) treatment (Delegard and Rinehart 1998). The presence of added sludge severely increased the concentrations of uranium, plutonium, and americium in the treated residues.…”

Section: Background and Approachmentioning

confidence: 97%

“…This material is identical, except for some incidental drying, to the material used in the prior testing of IX material leaching (Delegard and Rinehart 1998). As described in the previous report, the H-08 material was rinsed of adsorbed sludge particles.…”

Section: Materiaismentioning

confidence: 99%

“…The solids were drained on the sieve and the rinsed portions collected in a single jar. The rinsed material was designated H-08 BEAD G, and two sample aliquots were taken for analysis (analysis results in Delegard and Rinehart 1998).…”

Section: Materiaismentioning

confidence: 99%

“…The sludge that was added in two of the present experiments was the same sludge as used in the prior tests (KECOMP) except for some incidental drying (Delegard and Rinehart 1998). This material is a composite of canister sludges taken from the KE Basin.…”

Section: Materiaismentioning

confidence: 99%

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Distribution of Components in Ion Exchange Materials Taken from the K East Basin and Leaching of Ion Exchange Materials by Nitric/Hydrofluoric Acid and Nitric/Oxalic Acid

Delegard¹,

Rinehart²,

Hoopes³

1999

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Section: Background and Approachmentioning

confidence: 97%

Section: Materiaismentioning

confidence: 99%

Section: Materiaismentioning

confidence: 99%

Section: Materiaismentioning

confidence: 99%

See 2 more Smart Citations

Distribution of Components in Ion Exchange Materials Taken from the K East Basin and Leaching of Ion Exchange Materials by Nitric/Hydrofluoric Acid and Nitric/Oxalic Acid

Delegard¹,

Rinehart²,

Hoopes³

1999

Self Cite

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“…The IX material used in this work was excess material prepared for leaching investigations (Delegard and Rinehart 1998). Material from KES-H-08 was sieved and rinsed prior to testing to remove entrained sludge.…”

Section: Ion Exchange Materialsmentioning

confidence: 99%

Validation Testing of the Nitric Acid Dissolution Step Within the K Basin Sludge Pretreatment Process

Schmidt¹,

Delegard²,

Silvers³

et al. 1999

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Uranium Metal Analysis via Selective Dissolution

Delegard¹,

Sinkov²,

Schmidt³

et al. 2008

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SummaryUranium metal, which is present in sludge held in the Hanford Site K West Basin, can create hazardous hydrogen atmospheres during sludge handling, immobilization, or subsequent transport and storage operations by its oxidation/corrosion in water. A thorough knowledge of the uranium metal concentration in sludge therefore is essential to successful sludge management and waste process design.The goal of this work was to establish a rapid routine analytical method to determine uranium metal concentrations as low as 0.03 wt% in sludge even in the presence of up to 1000-fold higher total uranium concentrations (i.e., up to 30 wt% and more uranium) for samples to be taken during the upcoming sludge characterization campaign and in future analyses for sludge handling and processing. This report describes the experiments and results obtained in developing the selective dissolution technique to determine uranium metal concentration in K Basin sludge. The work described in this report:• provides a technical underpinning of the validity of the selective dissolution method, including the influence of various sludge components, in five test series using simulated and genuine sludges of widely varying composition• establishes analytical parameters (concentrations, quantities, temperatures, and times) necessary to develop the selective dissolution sludge-digestion analytical procedure.The uranium metal detection limit is estimated to be about 0.004 wt% based on the testing performed with actual sludge, thus meeting the goal detection limit of 0.03 wt%. The detection limit largely is established by the trace residual uranium carryover that exists in the leached and rinsed sludge. In the final series of method validation tests using actual K Basin sludge, spiked with uranium metal at concentrations ranging from 0.025 to 1.29 wt%, uranium metal recoveries averaged 99.4% with a standard deviation of 3.3%.

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Radionuclide Leaching from Organic Ion Exchange Resin

Cited by 3 publications

References 3 publications

Distribution of Components in Ion Exchange Materials Taken from the K East Basin and Leaching of Ion Exchange Materials by Nitric/Hydrofluoric Acid and Nitric/Oxalic Acid

Distribution of Components in Ion Exchange Materials Taken from the K East Basin and Leaching of Ion Exchange Materials by Nitric/Hydrofluoric Acid and Nitric/Oxalic Acid

Validation Testing of the Nitric Acid Dissolution Step Within the K Basin Sludge Pretreatment Process

Uranium Metal Analysis via Selective Dissolution

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