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Scientific basis for nuclear waste management XXII. Materials Research Society symposium proceedings: Volume 556

Conference ·
OSTI ID:20015733
Papers are arranged under the following topical sections: Development and characterization of ceramic waste forms; Ceramic waste form corrosion; Glass waste form processing; Glass formulation, properties, and structure; Glass waste form corrosion; Spent nuclear fuel; Performance assessment; Repository backfill; Flow and transport; Natural analogues; Container corrosion; Metal waste form corrosion; Radionuclide speciation and solubility; Radionuclide sorption; Microbial effects; Radiation effects; Cement waste forms; and Waste treatment. Papers have been processed separately for inclusion on the data base.
OSTI ID:
20015733
Country of Publication:
United States
Language:
English