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This report summarizes the potential options for the processing and disposal of mixed waste generated by reprocessing spent nuclear fuel at the Idaho Chemical Processing Plant. It compares the proposed waste-immobilization processes, quantifies and characterizes the resulting waste forms, identifies potential disposal sites and their primary acceptance criteria, and addresses disposal issues for hazardous waste.

Volume 2 contains the following topical sections: estimates of feed and waste volumes, compositions, and properties; evaluation of radionuclide inventory for Zr calcine; evaluation of radionuclide inventory for Al calcine; determination of k{sub eff} for high level waste canisters in various configurations; review of ceramic silicone foam for radioactive waste disposal; epoxides for low-level radioactive waste disposal; evaluation of several neutralization cases in processing calcine and sodium-bearing waste; background information for EFEs, dose rates, watts/canister, and PE-curies; waste disposal options assumptions; update of radiation field definition and thermal generation rates for calcine process packages of various geometries-HKP-26-97; and standard criteria of candidate repositories and environmental regulations for the treatment and disposal of ICPP radioactive mixed wastes.

The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE`s investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4).

The Other Generators category includes all greater-than-Class C low-level radioactive waste (GTCC LLW) that is not generated or held by nuclear utilities or sealed sources licensees or that is not stored at Department of Energy facilities. To determine the amount of waste within this category, 90 LLW generators were contacted; 13 fit the Other Generators category. Based on information received from the 13 identified Other Generators, the GTCC LLW Management Program was able to (a) characterize the nature of industries in this category, (b) estimate the 1993 inventory of Other Generator waste for high, base, and low cases, and (c) project inventories to the year 2035 for high, base, and low cases. Assumptions were applied to each of the case estimates to account for generators who may not have been identified in this study.

A summary of the research carried out prior to the start and during the first half of this project is presented. A description of the geothermal binary cycle and procedures for cycle thermodynamic analysis focusing on the question of resource utilization are discussed. General and specific criteria for preliminary selection of working fluids and operating conditions for binary cycles are considered in terms of equipment and working fluid costs and in terms of resource utilization efficiency. Steps are given for preliminary binary cycle design computations. Preliminary evaluations of alternative pure working fluid, ideal thermodynamic cycles are illustrated. The development of the working fluid mixture thermodynamic cycle, GEO 1, using the improved versions of previously developed thermodynamic properties routines was the first of several significant accomplishments during the first half of this project. Documentation of the thermodynamic properties program which can calculate densities, enthalpies, entropies, heat capacities, K-values for vapor and liquid mixtures (limited presently to hydrocarbons), flashes, dew and bubble points, isentropic and isenthalpic state changes, has been completed. Preliminary calculations using GEO 1 have indicated that mixture cycles yield greater net power output than either pure propane, isobutane, or isopentane cycles when equal heat exchanger log mean temperature differencesmore » are considered and also when optimized ideal cycles are compared. Steps to upgrade GEO 1 with equipment sizing and economics routines to produce GEO 2 and GEO 3 simulators were begun.« less