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Behavior of mercury in high-temperature vitrification processes

Journal Article · · Nuclear Technology; (United States)
OSTI ID:6910529
; ;  [1]
  1. Pacific Northwest Lab., Richland, WA (United States)
This paper reports that the Pacific Northwest Laboratory (PNL) has evaluated the waste processing behavior of mercury in simulated defense waste. A series of tests were performed under various operating conditions using an experimental-scale liquid-fed ceramic melter (LFCM). This solidification technology had no detectable capacity for incorporating mercury into its product, borosilicate glass. Chemically, the condensed mercury effluent was composed almost entirely of chlorides, and except in a low-temperature test, Hg[sub 2]Cl[sub 2] was the primary chloride formed. As a result, combined mercury accounted for most of the insoluble mass collected by the process quench scrubber. Although macroscopic quantities of elemental mercury were never observed in process secondary waste streams, finely divided and dispersed mercury that blackened all condensed Hg[sub 2]Cl[sub 2] residues was capable of saturating the quenched process exhaust with mercury vapor. The vapor pressure of mercury, however, in the quenched melter exhaust was easily and predictably controlled with the off-gas stream chiller.
DOE Contract Number:
AC06-76RL01830
OSTI ID:
6910529
Journal Information:
Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 100:3; ISSN 0029-5450; ISSN NUTYBB
Country of Publication:
United States
Language:
English