• nuclide loading of zeolites,

  • waste forms' acceptability and costs, and

  • testing and performance assessment of waste forms.

The essential elements of the process are that it be carried out by experts in the requisite fields, be independent, and be external to the process developers. Such experts could also assist ANL in defining the adequacy of the EBR-II demonstration criteria.

The committee also suggests active interaction with the international research groups engaged in similar work (e.g., on issues of zeolite technology, characterization of materials, and qualification testing). Currently, ANL researchers' interactions occur at professional meetings and scientific conferences. The committee suggests more formal and intensive interactions with experts in particular fields to maintain the highest level of science in the program.

References

Argonne National Laboratory (ANL). 1997. EBR-II Spent Fuel Treatment Demonstration Project: Work Breakdown Structure, Argonne, Ill. July.

Conca, J. L., B. A. Robinson, I. R. Triay, and G. Y. Bussod. 1997. “Direct Characterization of Transport Parameters in Near-Field and Engineered Backfill/Invert Materials Needed for Waste Isolation Strategies, ” in Scientific Basis for Nuclear Waste Management XX, W. Gray and I. Triay, eds., Materials Research Society, Pittsburgh, Pa.

Department of Energy (DOE), Office of Nuclear Energy, Science and Technology. 1996. Environmental Assessment: Electrometallurgical Treatment Research and Demonstration Project in the Fuel Conditioning Facility at Argonne National Laboratory-West, DOE/EA-1148, Washington, D.C., May 15.

McGrail, B.P., C. Lindenmeier, P. Martin, and G. Gee. 1997. “Accelerated Testing of Waste Forms Using a Novel Pressurized Unsaturated Flow (PUF) Method,” in Scientific Basis for Nuclear Waste Management XX,W. Gray and I. Triay, eds., Materials Research Society, Pittsburgh, Pa.

National Research Council (NRC). 1995a. A Preliminary Assessment of the Promise of Continued R&D into an Electrometallurgical Approach for Treating DOE Spent Fuel, National Academy Press, Washington, D.C.

National Research Council (NRC). 1995b. An Assessment of Continued R&D into an Electrometallurgical Approach for Treating DOE Spent Nuclear Fuel, National Academy Press, Washington, D.C.

National Research Council (NRC). 1996a. An Evaluation of the Electrometallurgical Approach for Treatment of Excess Weapons Plutonium, National Academy Press, Washington, D.C., February.

National Research Council (NRC). 1996b. Electrometallurgical Techniques for DOE Spent Fue



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ELECTROMETALLURGICAL TECHNIQUES FOR DOE SPENT FUEL TREATMENT: STATUS REPORT ON ARGONNE NATIONAL LABORATORY'S R&D ACTIVITY THROUGH SPRING 1997 nuclide loading of zeolites, waste forms' acceptability and costs, and testing and performance assessment of waste forms. The essential elements of the process are that it be carried out by experts in the requisite fields, be independent, and be external to the process developers. Such experts could also assist ANL in defining the adequacy of the EBR-II demonstration criteria. The committee also suggests active interaction with the international research groups engaged in similar work (e.g., on issues of zeolite technology, characterization of materials, and qualification testing). Currently, ANL researchers' interactions occur at professional meetings and scientific conferences. The committee suggests more formal and intensive interactions with experts in particular fields to maintain the highest level of science in the program. References Argonne National Laboratory (ANL). 1997. EBR-II Spent Fuel Treatment Demonstration Project: Work Breakdown Structure, Argonne, Ill. July. Conca, J. L., B. A. Robinson, I. R. Triay, and G. Y. Bussod. 1997. “Direct Characterization of Transport Parameters in Near-Field and Engineered Backfill/Invert Materials Needed for Waste Isolation Strategies, ” in Scientific Basis for Nuclear Waste Management XX, W. Gray and I. Triay, eds., Materials Research Society, Pittsburgh, Pa. Department of Energy (DOE), Office of Nuclear Energy, Science and Technology. 1996. Environmental Assessment: Electrometallurgical Treatment Research and Demonstration Project in the Fuel Conditioning Facility at Argonne National Laboratory-West, DOE/EA-1148, Washington, D.C., May 15. McGrail, B.P., C. Lindenmeier, P. Martin, and G. Gee. 1997. “Accelerated Testing of Waste Forms Using a Novel Pressurized Unsaturated Flow (PUF) Method,” in Scientific Basis for Nuclear Waste Management XX,W. Gray and I. Triay, eds., Materials Research Society, Pittsburgh, Pa. National Research Council (NRC). 1995a. A Preliminary Assessment of the Promise of Continued R&D into an Electrometallurgical Approach for Treating DOE Spent Fuel, National Academy Press, Washington, D.C. National Research Council (NRC). 1995b. An Assessment of Continued R&D into an Electrometallurgical Approach for Treating DOE Spent Nuclear Fuel, National Academy Press, Washington, D.C. National Research Council (NRC). 1996a. An Evaluation of the Electrometallurgical Approach for Treatment of Excess Weapons Plutonium, National Academy Press, Washington, D.C., February. National Research Council (NRC). 1996b. Electrometallurgical Techniques for DOE Spent Fue

OCR for page 18
ELECTROMETALLURGICAL TECHNIQUES FOR DOE SPENT FUEL TREATMENT: STATUS REPORT ON ARGONNE NATIONAL LABORATORY'S R&D ACTIVITY THROUGH SPRING 1997 National Research Council (NRC). 1997a. Electrometallurgical Techniques for DOE Spent Fuel Treatment: Fall 1996 Status Report on Argonne National Laboratory's R&D Activity, National Academy Press, Washington, D.C., March. National Research Council (NRC). 1997b. Evaluation of the U.S. Department of Energy's Alternatives for the Removal and Disposition of Molten Salt Reactor Experiment Fluoride Salts, National Academy Press, Washington, D.C.