[en] The following topics are considered: (1) cryosorption vacuum pumping for fusion reactors, (2) TNS support studies, (3) tritium recovery from irradiated Li-Al and SAP, (4) actinide oxides, nitrides, and carbides, and (5) transition metal-actinide-C phase equilibria

[en] Program activities and publications prepared in the reactor safety, radiation-release guidelines, safeguards, plutonium recycle, and waste management studies are briefly described

[en] Forward and reverse extraction rates of U and Th were determined as a function of TBP concentration

[en] This program is concerned with the development of biochemical engineering technology whereby individual process steps, at least one of which utilizes a biological entity, can be integrated to result in a highly useful overall process. Areas of concern to DOE that will benefit directly from this technology include energy production and conservation, resource recovery, and pollution abatement. Investigations specific to problems in nuclear waste management include the removal of radionuclides and chemical contaminants from aqueous process and effluent streams. Bioengineering research activities were focused on three areas during this reporting period: enzyme catalysis; treatment of aqueous effluents from coal conversion processes; and bioreactor scale-up and process modeling studies

[en] 1,1,1,2,2,3,3-heptafluoro-7,7-dimethyl-4,6-octanedione (HFDMOD) is being studied for extracting cations. Methods and agents for separating actinides from U ore processing streams and fuel reprocessing wastes are being studied. Zinc in HEPA filters was found to increase penetration by alpha-active materials. Distribution data are given for the extraction of acetic acid by amines, of alkali metals by HDEHP and crown ethers, of Eu by DEHDECMP, and of alkali and alkaline-earth metals by HFDMOD. Removal of tritium from lithium by sorption on yttrium was studied

[en] Program activities are discussed under the following topics: Transuranium Processing Plant operations; special projects; stable isotope operations; and separator research and development

[en] Work in the following fields is reported: partitioning and transmutation, removal and segregation of radionuclides and nitrates from liquid wastes, removal of organic contaminants and tritium from fuel reprocessing effluent streams, fixation of wastes in concretes, cement grouts for waste sludge disposal by hydrofracture, cements for plugging boreholes, updating ORIGEN, projection of wastes from fuel cycle, and assistance to OWI

[en] Covered are: ²³³U processing, plans for drop testing of spent fuel cask, plans for converting old U solution to U₃O₈, nuclear safety assistance, and BNFP applicability study

[en] Research on the Sol-Gel Sphere-Pac method of fuel fabrication is reported. Methods for preparing fuel microspheres are reviewed. Experimental studies are being conducted on preparing UO₂ and UO₂--PuO₂ microspheres