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This document is one of a series of technical progress reports designed to report on radioactive waste management programs at Pacific Northwest Laboratory. These programs are funded by the Department of Energy's Office of Nuclear Waste Management. Only programs in the scope of this document that have significant, reportable results are included.

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This rcpctt was prcparcd a an account cf work s p n s e k by th* United S u t e Gwemmmt.

Much emphasis continues to be on the transfer of remote design technology for components integral to the West Valley Demonstration Project's (WVDP) vitrification process. In addition to preparing equipment specifications and drawings, Pacific Northwest Laboratory (PNL) staff also participated in numerous design coordination meetings and reviews of drawings prepared by other WVDP contractors. vitrification cell were prepared by this program in FY 1988. jumpers connect vessels in the cell to each other for the transfer of solutions and provide for the flow of materials, instrumentation signals, and power from outside the cell. Analysis required in preparing the jumper designs involved balance, thermal stress, seismic, set-down stress, and di spl acement cal cul ati ons. Nearly 200 jumper drawings for the The remote Design efforts were begun on the canister decontamination and swipe station and on the remote maintenance station. layouts of the vitrification off-gas treatment system, including a reamer to remotely clean the melter off-gas line, were finalized. Also finalized were the designs for the high-efficiency particulate air (HEPA) filter assemblies for heating, cooling and air conditioning of the vitrification cell. Modifications to the waste feed slurry pump and the backup remote slurry Equipment selection and sampler were completed. Conceptual designs for two a1 ternative viewing systems to monitor the radioactive glass stream during filling of canisters were prepared as part of a feasibility study. inside of the melter was fabricated, functionally tested in a remote mockup, and delivered to West Valley Nuclear Services. Conceptual drawings and engineering design criteria were issued for the suction canister that will be used to empty the melter at the end of the vitrification campaign. The viewing system for the Samples of actual West Valley high-level radioactive waste were received and characterized. washing, ion-exchange and blending steps for the project were conducted. Other support work included preparation o f a vitrification process Laboratory process tests dupl icating the planned sludge i i i description document, a detailed testing plan identifying and prioritizing the testing needs at West Valley to prepare for startup of vitrification, and review of the supernatant treatment system operations. Analysis and documentation of the mixing capability tests for the melter feed system were completed. fl owsheet was devel oped. Software used in mass balance calculations for the vitrification Support for the product qualification activities continued. tically designed study was completed that prepared and tested a set of glasses representing the expected range of operational variability in waste and glass composition. model of the leachability of the glass as a function of its chemical composition. A statis-This work is providing data to build a statistical FABRICATION OF ISOTOPIC HEAT AND RADIATION SOURCES Production of the 32 heat and radiation source canisters for the Federal Republic of Germany (FRG)...