The kinetics of the reaction of nitrite ion in bisulfite solutions to form hydroxylaminedisulfonate have been investigated. Evidence has been presented that nitrososulfonic acid is the probable intermediate in this reaction and that it can undergo sulfonation or hydrolysis reactions. The hydrolysis reaction yields N20 under the present conditions of study (acid solutions), which complicates the determination of the rate of formation of hydroxylaminedisulfonate. The ratio of the rate constants for sulfonation and hydrolysis (kA/kB) is 1.7 ± 0.5. The previously determined rate law for the formation of the disulfonate has been verified, although one term has been shown to be absent when phthalate, oxalate, or tartrate buffer systems are used to maintain the desired acidity.

The reaction between nitrite and bisulfite to form hydroxylamine disulfonate has been investigated and found to consist of three concurrent processes.TI1e reaction rate law can be expressed as d [HADS]

No abstract

Twenty-three of the 63 monitoring wells in the 643-G burial ground consistently contain measurable (> 1 ppm) amounts of total organic carbon, TOC. Of these 23 wells, 10 that contain elevated (2-400 ppm) TOC were chosen for in-depth analysis of semivolatile organics by gas chromatography/mass spectrometry, GC/MS. A well located near the site of previous decontamination operations was also chosen for analysis. About 40% of the organic compounds detected in these well waters have been identified. Many of these compounds are indicative of liquid scintillation wastes, spent solvent wastes, and solvent degradation products. Four priority pollutants were present at low levels. Some of the organics identified are probably degradation products from humic substances. Organic compounds of unknown origin are also present. No strong chelators capable of increasing radionuclide mobility have been identified. Preliminary dialysis work indicates that up to 30-40% of the TOC may be present as nonvolatile humic substances that cannot be analyzed by GC/MS.

Waste salt solution, produced during processing of high-level nuclear waste, will be incorporated in a cement matrix for emplacement in an engineered disposal facility. Wasteforrn characteristics and disposal facility details will be presented along with results of a field test of wasteform contaminant release and of modeling studies to predict releases.