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Title: Leach testing of Idaho Chemical Processing Plant final waste forms

Conference ·
OSTI ID:5143449

A number of pellets and highly durable glasses prepared from nonradioactive-simulated high-level wasste calcines have been leach tested. The leach tests are patterned on the IAEA standard test and the proposed Materials Characterization Center tests. Most tests are made with static distilled water at 25, 70, 95, 250, and 350/sup 0/C and in refluxing distilled water, Soxhlet, at 95/sup 0/C. Leach rates are determined by analyzing the leachate by instrumental activation analysis or spectrochemical analysis and from weight loss. Leaches are run on glass using cast and core drilled cylinders, broken pieces and coarse ground material. Sample form has a considerable effect on leach rates; solid pieces gave higher leach rates than ground glass when expressed in g/cm/sup 2//day. Cesium, molybdenum and weight loss leach rates of cast glass cylinders in distilled water varied from <10/sup -7/ g/cm/sup 7//day at 25/sup 0/C to approx. 10/sup -3/ g/cm/sup 2//day at 250/sup 0/C. The leach rates in static distilled water at 95/sup 0/C were considerably lower than those in refluxing distilled water, Soxhlet, at the same temperature. Even at 25/sup 0/C, sodium, cesium, and molybdenum readily leached from the porous pellets, but the pellets showed no visible attack, even at 250/sup 0/C.

Research Organization:
Exxon Nuclear Idaho Co., Inc., Idaho Falls (USA)
DOE Contract Number:
AC07-79ID01675
OSTI ID:
5143449
Report Number(s):
CONF-800987-2; TRN: 80-016598
Resource Relation:
Conference: Workshop on comparative leaching behavior of radioactive waste forms, Argonne, IL, USA, 3 Sep 1980
Country of Publication:
United States
Language:
English