[en] The process off-gas filter system designed for use in the New Waste Calcining Facility (NWCF) requires remote filter removal, replacement and in-place DOP testing. A series of full-scale mockup tests, modifications and retesting at the Remote Maintenance Development Facility (RMDF) resulted in a system in which a commercial High Efficiency Particulate Air (HEPA) filter can be installed, tested for leaks, operated and removed from a sealed filter housing using remote handling methods. This paper describes the development, testing and results of this effort

[en] Increased emphasis on lowering personnel radiation exposures to as-low-as-reasonably-achievable (ALARA) and on containment of radioactive materials influenced a special emphasis on remotely operated sampling systems for the New Waste Calcining Facility (NWCF). This paper describes work done by Allied Chemical Corporation in designing and testing remote solid, liquid and gas sampling systems for the NWCF. Work also included a transfer system for transferring samples to an analytical facility. Remote maintenance capabilities were designed into the system so that any failure prone component or subassembly could be remotely removed and replaced

[en] Increased emphasis on lowering personnel radiation exposures to as low as reasonably achievable and on containment of radioactive materials influenced a special emphasis on remotely operated sampling systems for the New Waste Calcining Facility (NWCF). Work done by Allied Chemical Corporation in designing and testing remote solid, liquid, and gas sampling systems for the NWCF is described. Work also included a transfer system for transferring samples to an analytical facility. Remote maintenance capabilities were designed into the system so that any failure-prone component or subassembly could be remotely removed and replaced

[en] Acid high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the US Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage ate the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal

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[en] Irradiated nuclear fuel has been reprocessed at the Idaho Chemical Processing Plant (ICPP) since 1953 to recover uranium-235 and krypton-85 for the US Department of Energy (DOE). The resulting acidic high-level radioactive waste (HLW) has been solidified to a calcine since 1963 and stored in stainless steel underground bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage at the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Processing, Calcine Immobilization, and Metal Recycle/Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal

[en] This paper describes the iterative process of grouping and performance assessment that has led to the current grouping of the U.S. Department of Energy (DOE) spent nuclear fuel (SNF). The unique sensitivity analyses that form the basis for incorporating DOE fuel into the total system performance assessment (TSPA) base case model are described. In addition, the chemistry that results from dissolution of DOE fuel and high level waste (HLW) glass in a failed co-disposal package, and the effects of disposal of selected DOE SNF in high integrity cans are presented

[en] Acidic high-level radioactive waste (HLW) resulting from fuel reprocessing at the Idaho Chemical Processing Plant (ICPP) for the U.S. Department of Energy (DOE) has been solidified to a calcine since 1963 and stored in stainless steel bins enclosed by concrete vaults. Several different types of unprocessed irradiated DOE-owned fuels are also in storage at the ICPP. In April, 1992, DOE announced that spent fuel would no longer be reprocessed to recover enriched uranium and called for a shutdown of the reprocessing facilities at the ICPP. A new Spent Fuel and HLW Technology Development program was subsequently initiated to develop technologies for immobilizing ICPP spent fuels and HLW for disposal, in accordance with the Nuclear Waste Policy Act. The Program elements include Systems Analysis, Graphite Fuel Disposal, Other Spent Fuel Disposal, Sodium-Bearing Liquid Waste Minimization. This paper presents an overview of the ICPP radioactive wastes and current spent fuels, with an emphasis on the description of HLW and spent fuels requiring repository disposal

[en] A Performance Assessment (PA) by Sandia National Laboratories evaluated various combinations of spent nuclear fuels and high-level waste forms (both current and expected) for their performance against 40CFR191 (as promulgated in 1985) requirements in two hypothetical, geologic repositories. The packaged waste forms evaluation modeled canister corrosion, waste form behavior after canister breach, and transport of materials within the repository boundaries. In all cases studied in salt, human intrusion demonstrated the greatest potential for release to the environment and offered the only condition of release to the environment beyond the repository boundary within the 10,000 year time frame identified in the regulation