Published April 1996 | Version v1
Report Open

Fiscal year 1995 laboratory scale studies of Cs elution in Tank 8D-1 and sludge dissolution in tank 8D-2

Description

During Phase I of West Valley Demonstration project waste remediation, an estimated 95% of the zeolite currently in tank 8D-1 will be transferred to tank 8D-2, leaving behind residual Cs-loaded zeolite which will require treatment to remove the Cs. After phase I vitrification, tank 8D-2 will contain residual waste from PUREX and THOREX and spent Cs-loaded zeolite. The residual waste will require treatment. Oxalic acid has been proposed for eluting Cs from zeolite in tank 8D-1 and dissolving radionuclides in tank 8D-2. Laboratory tests were performed to determine optimum Cs elution and sludge dissolution conditions and to evaluate effects of multiple contacts, long-term contacts, presence of corrosion products, lack of agitation, temperature of tank contents, and oxalic acid concentration. Mild steel corrosion tests were also conducted

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96009900; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
257 p.
Report number
PNNL--10945

Optional Information

Contract/Grant/Project number
Contract AC06-76RL01830
Funding organization
USDOE, Washington, DC (United States).