Properties of Saltstone Prepared Containing H-Canyon Waste

Cozzi, A

Savannah River Site (S.C.)

关键词: Leaching;    12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities;    Radioactive Waste Processing;    Leachates;    Mercury;   

DOI  :  10.2172/890168
RP-ID  :  WSRC-TR-2005-00149R0
RP-ID  :  DE-AC09-96SR18500
RP-ID  :  890168

美国|英语

来源: UNT Digital Library

【 摘 要 】

Saltstone slurries were prepared from solutions made from H-Canyon waste and evaluated for processing properties. Salt solutions prepared with a 1:1 ratio of Tank 50H simulant and H-Canyon blended waste produced slurries that met the processing requirements in Table 2 of the Task Technical and Quality Assurance Plan (TTQAP). Additions of set retarder and antifoam were necessary to meet these processing requirements. The water to premix ratio used to achieve acceptable processing properties was 0.63. Slurries prepared solely with H-Canyon blended waste as the salt solution met the gel time and bleed water requirements, but did not set in the allotted time. Compressive strength samples prepared from the mix with acceptable processing properties had an average compressive strength of 814 psi (Samples with a compressive strength value of >200 psi are acceptable.). Analysis for mercury of the leachate of samples analyzed by the Toxic Characteristic Leaching Procedure (TCLP) indicated a concentration of mercury in the leachate <0.11 mg/L (The limit set by the Environmental Protection Agency (EPA) Resource Conservation and Recovery Act (RCRA) for mercury to require treatment is 0.2 mg/L.). It is recommended that without further testing; Tank 50H be limited to no more than 50 wt% H-Canyon material. It is also recommended that prior to the transfer of Tank 50H to the Saltstone Processing Facility; a sample of the Tank 50H waste be evaluated for processing properties.