Open AccessFiscal year 1995 laboratory scale studies of Cs elution in Tank 8D-1 and sludge dissolution in tank 8D-2
Author(s) -
J.A. Sills,
G.K. Patello,
J.S. Roberts,
K.D. Wiemers,
M.R. Elmore,
W.G. Richmond,
Renee L. Russell
Publication year - 1996
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/212676
Subject(s) - oxalic acid , dissolution , corrosion , waste management , vitrification , elution , zeolite , storage tank , purex , chemistry , residual , nuclear chemistry , environmental science , materials science , pulp and paper industry , metallurgy , chromatography , extraction (chemistry) , engineering , inorganic chemistry , solvent extraction , medicine , biochemistry , andrology , catalysis , algorithm , computer science
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
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