Appendix A
Documents Received During This Study

Alternative Waste Form Peer Review Panel. 1979. The Evaluation and Review of Alternative Waste Forms for Immobilization of High Level Radioactive Wastes. Washington, D.C.: U.S. Department of Energy Office of Nuclear Waste Management.

Australian Nuclear Science and Technology Organization (ANSTO). 1997-1998. ANSTO's Annual Report. Sydney, Australia.


Barnes, C. M., D. D. Taylor, and B. R. Helm. 1997. Transmittal of Process Basis Information for the Feasibility Study of the Preferred Alternative for Treatment of ICCP Sodium-Bearing Wastes, Calcine and Low-Level Wastes (CMB-01-97; interdepartmental communication, April). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.

Barrer, R. M., and J. F. Cole. 1970. Chemistry of soil minerals. Pan VI. Salt entrainment by sodalite and cancrinite during their synthesis. Chemical Society Journal. No.s 2:7-12 Pp. 1516-1523.

Barrer, R. M., J. F. Cole, and H. Villiger. 1970. Chemistry of soil minerals . Pan VII. Synthesis, properties, and crystal structures of salt-filled cancrinites. Chemical Society Journal No.s 2:7-12. Pp. 1523-1531.

Bell, J. T. 1998. Alternatives to HLW Vitrification: The Need for Common Sense. Presentation given at SPECTRUM '98 September 13-18, in Denver, Colorado. Bell Consultants.

Berreth, J. R. 1988. Inventories and Properties of ICPP Calcined High-Level Waste. (WINCO 1050; February). Idaho Falls, Idaho: U.S. Department of Energy/Westinghouse Idaho Nuclear Company, Inc.

Bonano, E. J., M. S. Y. Chu, L. L. Price, S. H. Conrad, and P. T. Dickman. 1991. The Disposal of Orphan Wastes Using the Greater Confinement Disposal Concept (DE-Ac04-76DP00789). Sandia National Laboratories Albuquerque, NM: U.S. Department of Energy.

Bonniaud, R., P. Labe, and C. Sombret. 1968. Vitrification des residus solides fluores provenant de l'attaque par le fluor des combustibles irradies. Presentation given at the Symposium sur le Retraitement par Voie Seche on October 29 in Mol, Belgium.

Bosley, J. 1998. Closure Study for the Liquid Effluent Treatment and Disposal Facility Building CPP-1618 (INEEL/EXT-98-01152; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.



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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Appendix A Documents Received During This Study Alternative Waste Form Peer Review Panel. 1979. The Evaluation and Review of Alternative Waste Forms for Immobilization of High Level Radioactive Wastes. Washington, D.C.: U.S. Department of Energy Office of Nuclear Waste Management. Australian Nuclear Science and Technology Organization (ANSTO). 1997-1998. ANSTO's Annual Report. Sydney, Australia. Barnes, C. M., D. D. Taylor, and B. R. Helm. 1997. Transmittal of Process Basis Information for the Feasibility Study of the Preferred Alternative for Treatment of ICCP Sodium-Bearing Wastes, Calcine and Low-Level Wastes (CMB-01-97; interdepartmental communication, April). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Barrer, R. M., and J. F. Cole. 1970. Chemistry of soil minerals. Pan VI. Salt entrainment by sodalite and cancrinite during their synthesis. Chemical Society Journal. No.s 2:7-12 Pp. 1516-1523. Barrer, R. M., J. F. Cole, and H. Villiger. 1970. Chemistry of soil minerals . Pan VII. Synthesis, properties, and crystal structures of salt-filled cancrinites. Chemical Society Journal No.s 2:7-12. Pp. 1523-1531. Bell, J. T. 1998. Alternatives to HLW Vitrification: The Need for Common Sense. Presentation given at SPECTRUM '98 September 13-18, in Denver, Colorado. Bell Consultants. Berreth, J. R. 1988. Inventories and Properties of ICPP Calcined High-Level Waste. (WINCO 1050; February). Idaho Falls, Idaho: U.S. Department of Energy/Westinghouse Idaho Nuclear Company, Inc. Bonano, E. J., M. S. Y. Chu, L. L. Price, S. H. Conrad, and P. T. Dickman. 1991. The Disposal of Orphan Wastes Using the Greater Confinement Disposal Concept (DE-Ac04-76DP00789). Sandia National Laboratories Albuquerque, NM: U.S. Department of Energy. Bonniaud, R., P. Labe, and C. Sombret. 1968. Vitrification des residus solides fluores provenant de l'attaque par le fluor des combustibles irradies. Presentation given at the Symposium sur le Retraitement par Voie Seche on October 29 in Mol, Belgium. Bosley, J. 1998. Closure Study for the Liquid Effluent Treatment and Disposal Facility Building CPP-1618 (INEEL/EXT-98-01152; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.

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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Brass, L. 1998. Foster Wheeler discusses project. Oak Ridge, Tenn.: The Oak Ridger. October 15. Brewer, K. N., R. S. Herbst, T. J. Tranter, A. L. Olson, T. A. Todd, I. D. Goodwin, and C. W. Lundholm. 1995. Dissolution of two NWCF calcines: extent of dissolution and characterization of undissolved solids. Idaho National Engineering Laboratory (INEL-95/0098; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Brewer, K. N., T. A. Todd, A. L. Olson, D. J. Wood, V. M. Gelis, E. A. Kozlitin, and V. V. Milyutin. 1996. Cesium removal from radioactive idaho chemical processing plant acidic waste with potassium copper hexacyanoferrate (INEL-96/0356; November). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Brewer, K. N., R. D. Tillotson, P. A. Tullock, T. G. Gain, R. S. Herbst, J. D. Law, T. A. Todd, and A. L. Olson. 1997. Elimination of Phosphate and Zirconium in the High-Activity Fraction Resulting from TRUEX Partitioning of ICPP Zirconium Calcines. Idaho National Engineering Laboratory (INEEL/EXT-97-00836; July). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Brewer, K. N., A. L. Olson, W. S. Roesener, and J. L. Tonso. 1997. Experimental results of calcine dissolution studies performed during FY-94, 95 (INEL-97-01192; September). Idaho Fails, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Brotzman J. R. 1978. Vitrification of high-level alumina nuclear waste. P. 215 in Scientific Basis for Nuclear Waste Management II, C. J. M. Northrup, Jr., ed. New York: Plenum Press. Brownell, L. E., C. H. Kindle, and T. L. Theis. 1973. Review of Literature Pertinent to the Aqueous Conversion of Radionuclides to Insoluble Silicates with Selected References and Bibliography (Revised) (ARH-2731 REV; December). Richland, Wash.: U.S. Atomic Energy Commission. Campbell, D. O., and D. D. Lee. 1991. Treatment Options and Flowsheets for ORNL Low-Level Liquid Waste Supernate (December-ORNL/TM-11800). Oak Ridge, Term.: Oak Ridge National Laboratory. Campbell, D. O., D. D. Lee, and T. A. Dillow. 1991. Development Studies for the Treatment of ORNL Low-Level Liquid Waste (November-ORNL/TM-11798). Oak Ridge, Tenn.: Oak Ridge National Laboratory. Chen, F., and D. E. Day. 1999. Corrosion of Selected Refractories by Iron Phosphate Melts, Ceramic Transactions 93:213-218. Childs, K. F., R. I. Donovan, and M. C. Swenson. 1982. The ninth processing campaign in the waste calcining facility. (DE-AC07-79IDO1675; April). Idaho Falls, Idaho: U.S. Department of Energy. Cochran, J. R. 1997. Letter (March 20) to Darryl Siemer of LMITCO, regarding Cementitious High-Level Waste and 40 CFR 268.40. Albuquerque, N. Mex.: Sandia National Laboratories. U.S. Department of Energy. Cochran, J., B. Crowe, and F. DiSanza. 1999. Intermediate depth burial of classified transuranic wastes in arid alluvium (abstract). Albuquerque, N.Mex.: Sandia National Laboratories. Cole, H. S., and E. L. Colton. 1982. Comparison of candidate glasses to vitrify ICPP calcined alumina waste. Transactions of the American Nuclear Society 43:109-110. Dafoe, R. E., and S. J. Losinski. 1998. Direct Cementitious Waste Option Study Report INEEL/EXT-97-01399; February). Idaho Fails, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.

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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Dafoe, R. E., D. A. Lopez, and K. L. Williams. 1997. DPC Loa .ding Feasibility Study Report (INEEL/EXT-97-01251; November). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company. Dahlmeir, M. M., L. C. Tuott, B. C. Spaulding, S. P. Swanson, K. D. McAllister, K. C. Decoria, S. L. Coward, R. J. Turk, R. A. Adams, and C. W. Barnes. 1998. Calcined Solids Storage Facility Closure Study (INEEL/EXT-97-01396 February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Davis, P. 1993. Letter (March 2) to Darryl Siemer of Westinghouse Idaho Nuclear Company, regarding greater confinement disposal of radioactive waste. Albuquerque, NM: Sandia National Laboratories. U.S. Department of Energy. Day, D. E., Z. Wu, C. S. Ray, and P. Hrma. 1999. Chemically durable iron phosphate glass wasteforms. Journal of Non-Crystalline Solids 241:1-12. Delegard, C. H., and G. S. Barney. 1975. Fixation of Radioactive Waste by Reaction With Clays: Progress Report (ARH-2731 REV; July). Richland, Wash.: U.S. Energy Research and Development Administration/Atlantic Richfield Hartford Company. Dirk, W. J. 1994. Long-Term Laboratory Corrosion Monitoring of Calcine Bin Set Materials Exposed to Zirconia Calcine. Idaho Falls, Idaho: U.S. Department of Energy/Westinghouse Idaho Nuclear Company, Inc. Dole, L. R., G. C. Rogers, M. T. Morgan, D. P. Stinton, J. H. Kessler, S. M. Robinson, and J. G. Moore. 1983. Cement-Based Radioactive Waste Hosts Formed under Elevated Temperatures and Pressures (Fuetap Concretes) for Savannah River Plant High-Level Defense Waste (ORNL/TM-8579; March). Oak Ridge, TN: Oak Ridge National Laboratory. Fluor Daniel, Inc. 1996. Sodium Waste Alternative Treatment and Disposal Feasibility Study (94-29-FT-008; April 1996 and addendum of July 1996). Idaho Falls, Idaho: U.S. Department of Energy Idaho Field Office. Fluor Daniel, Inc. 1997. Idaho Chemical Processing Plant Waste Treatment Facilities Feasibility Study Report, Volumes I & II. Idaho Falls, Idaho: DOE-Idaho Field Office. Fluor Daniel Hartford, Inc. 1998. Hanford Site Solid Waste Acceptance Criteria for June 29 (Document No. HNF-EP-0063). Available at URL: http//www.hanford.gov. Gahlert, S., and G. Ondracek. 1988. Sintered Glass. Pp. 161-192 in Radioactive Waste Forms for the Future, W. Lutze and R. C. Ewing, eds. Amsterdam: North-Holland. Garcia, R. S. 1997. Waste Inventories/Characterization Study. (INEL/EXT-97-00600; September). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company. Godfrey, R. 1999. Letter (February 16) to Thomas Kiess of the National Research Council, regarding the Australian Nuclear Science and Technology Organization's (ANSTO's) SYNROC ceramics technology. Embassy of Australia Office of the General Counsellor, Washington, D.C. Gougar, M. L. D., D. D. Siemer, and B. E. Scheetz. 1995. Vitrifiable Concrete for Disposal of Spent Nuclear Fuel Reprocessing Waste at I.N.E.L. Proceedings of the Materials Research Society Annual Meeting Symposium on the Scientific Basis for Nuclear Waste Management XIX. Idaho Falls, Idaho: Idaho National Engineering and Environmental Laboratory. Gougar, M. L. D., D. D. Siemer, and B. E. Scheetz. 1996. Vitrifiable concrete for disposal of spent nuclear fuel reprocessing waste at INEL. Pp. 359-366 in Proceedings of the Embedded Topical Meeting on DOE Spent Nuclear Fuel and Fissile Material Management. Reno, NV: American Nuclear Society.

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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Gougar, M. L. D., B. E. Scheetz, and D. D. Siemer. 1999. A novel waste form for disposal of spent nuclear reprocessing waste: A vitrifiable cement . Nuclear Technology, January. Guerrero A., S. Hérnandez, and S. Goñi. 1998. Durability of cement-based materials in simulated radioactive liquid waste: Effect of phosphate, sulphate and chloride ions. Journal of Materials Research 13(8):2151-2160. Grutzeck, M. W., and D. D. Siemer. 1997. Zeolites synthesized from class F fly ash and sodium aluminate slurry. Journal of the American Ceramic Society 809:2449-2453. Haley, D. J. 1998. Engineering Study Report for RCRA Facility Closure of CPP-604 (Process Equipment Waste Evaporator) and CPP-605 (INEEL/EXT-98-00151; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Harjula, R., J. Lehto, E. H. Tusa, and A. Paavola. 1994. Industrial Scale Removal of Cesium with Hexacyanoferrate Exchanger-Process Development, Nuclear Technology (September) 107:272-284. Hayward, P. J. 1988. Glass-Ceramics Pp. 427493 in Radioactive Waste Forms for the Future, W. Lutze and R. C. Ewing, eds. Amsterdam: North-Holland. Heimann, R. B., and T. T. Vandergraaf. 1988. Cubic zirconia as a candidate waste form for actinades-dissolution studies. Journal of Nuclear Material 7:583-586. Heiser, M. B. 1998. Tank Closure. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review meeting on October 1-2, at the U.S. DOE Idaho Operations Office, Idaho Falls, Idaho. Herbst, R. S., D. S. Fryer, K. N. Brewer, C. K. Johnson, and T. A. Todd. 1995. Experimental Results: Pilot Plant Calcine Dissolution and Liquid Feed Stability (INEL/EXT-95/0097; February). Idaho Falls, Idaho: U.S. Department of Energy (DOE)/Lockheed Martin Idaho Technologies Company. Herbst, R .S., K. N. Brewer, T. G. Garn, J. D. Law, R. T. Tillotson, and T. A. Todd. 1996. A Comparison of TRUEX and CMP Solvent Extraction Processes for Actinide Removal From ICPP Wastes (INEL-96/0094; April). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company. Herbst, R. S., J. D. Law, K. N. Brewer, T. A. Todd, and L. G. Olson. 1997. TRUEX Flowsheet Testing for the Removal of the Actinides from Dissolved ICPP Zirconium Calcine Using Centrifugal Contactors (INEL/EXT-97-00837; December). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company. Herbst, R. S., J. D. Law, and K. N. Brewer. 1998. Baseline TRUEX Flowsheet Development for the Removal of the Actinides from Dissolved INTEC Calcine Using Centrifugal Contactors (INEL/EXT-984)0833; August). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company. Idaho National Engineering and Environmental Laboratory (INEEL). 1997. Annual Update Review Copy INEEL Site Treatment Plan. Idaho Falls, Idaho: U.S. Department of Energy Idaho National Engineering and Environmental Laboratory. Jostsons, A., E. R. Vance, and R. Hutchings. 1996. Hartford HLW Immobilization in SYNROC (abstract). Sydney, Australia: Australian Nuclear Science and Technology Organization. Jostsons, A., E. Vance, and G. Durance. 1997. The Role of SYNROC in Partitioning and Conditioning Strategies in Radioactive Waste Management (abstract). Sydney, Australia: Australian Nuclear Science and Technology Organization.

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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Kimmel, R. 1999a. Letter (January 14) to Tom Kiess of the National Research Council, regarding information request and response to e-mail (EIS-99-002). Idaho Falls, Idaho: U.S. Department of Energy. Kimmel, R. 1999b. Letter (March 17) to Tom Kiess of the National Research Council, regarding requesting clarification on separations factors (DFs) as described in the Fluor Daniel study (DOE/ID/13206) (EIS-99-027). Idaho Fails, Idaho: U.S. Department of Energy. Kimmel, R. 1999c. Letter (November 16) to Tom Kiess of the National Research Council, regarding Dr. Tom Kiess' electronic mail, dated November 12, 1999, to A. Olson requesting clarification of earlier submitted data (OPE-EIS-994)77). Idaho Falls, Idaho: U.S. Department of Energy. Kirk, R., and D. Othmer, eds. 1992. Encyclopedia of Chemical Technology, 4th Ed., 1st Rev. New York: John Wiley & Sons 2:557 Knecht, D. A., P. C. Kong, and T. P. O'Holleran. 1996. Proposed Glass-Ceramic Waste Forms For Immoblizing Excess Plutonium. DOE Spent Nuclear Fuel & Fissile Material Management Meeting in Reno, NV, June 16-20. La Grange Park, Ill.: American Nuclear Society. Knecht, D. A., M. D. Staiger, J. D. Christian, C. L. Bendixsen, G. W. Hogg, and J. R. Berreth. 1997. Historical fuel reprocessing and HLW Management in Idaho. Radwaste Magazine 4:36-47. Knecht, D. A., K. Vinjamuri, S. V. Raman, B. A. Staples, and J. D. Grandy, S. Johnson, T. P. O'Holleran, and S. Frank. 1998. Summary of HLW Glass-Ceramic Waste Forms Developed in Idaho for Immobilizing Plutonium (abstract). Presentation given at the Waste Management '98 conference on March 2 in Tucson, Arizona. Knecht, D. 1998. Presentation given at National Research Council Committee's INEEL High-Level Waste Alternative Treatments Review meeting on August 17, at the Idaho Nuclear Technology and Engineering Center (INTEC). Idaho Falls, Idaho. Knecht, D., J. Valentine, A. Luptak, M. Staiger, H. Loo, and T. Wichmann. 1999. Options for Determining Equivalent MTHM for DOE High-Level Waste (INEEL/EXT-99-00317; March). Idaho Falls, Idaho: U.S. Department of Energy Idaho National Engineering and Environmental Laboratory. Landman, Jr., W. H., P. W. Bragassa, M. Spinti, M. Pope, and K. Wells. 1997. New Waste Calcining Facility Deactivation Option for Low-Level Waste Grout Disposal (INEEL/EXT-97-01076; December). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Landman, W. H. Jr., and C. M. Barnes. 1998. TRU Separations Options Study Report (INEEL/EXT-97-01428; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Law, J. D., K. N. Brewer, R. S. Herbst, T. A. Todd. 1996. Demonstration of the TRUEX Process for Partitioning of Actinides from Actual ICPP Tank Waste Using Centrifugal Contactors in a Shielded Cell Facility (INEL-96/0353; September). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Law, J. D., and D. J. Wood. 1996. Development and Testing of a SREX Flowsheet for the Partitioning of Strontium and Lead from Simulated ICPP Sodium-Bearing Waste (INEL-96/0437; November). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Law, J. D., D. J. Wood, L. G. Olson, and T. A. Todd. 1997. Demonstration of a SREX Flowsheet for the Partitioning of Strontium and Lead from Actual ICPP Sodium-Bearing Waste (INEEL/EXT-97-00832; August). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.

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Alternative High-Level Waste Treatments at the Idaho National Engineering and Environmental Laboratory Law, J. D., K. N. Brewer, R. S. Herbst, T. A. Todd, and L. G. Olson. 1998. Demonstration of an Optimized TRUEX Flowsheet for Partitioning of Actnides from Actual ICPP Sodium-Beating Waste Using Centrifugal Contactors in a Shielded Cell Facility (INEEL/EXT-98-00004, January). Idaho Falls, Idaho: U.S. Department of Energy /Lockheed Martin Idaho Technologies Company. Lee, A. E., and D. D. Taylor. 1998. Cementitious Waste Option Scoping Study Report (INEEL/EXT-97-01400; February). Idaho Falls, Idaho: U.S. Department of Energy /Lockheed Martin Idaho Technologies Company. Lockheed Martin Idaho Technologies Company (LMITCO). 1996. High-Level Waste Program Plan (INEL-96/122; April). Idaho Falls, Idaho: U.S. Department of Energy/LMITCO. Lockheed Martin Idaho Technologies Company. 1998. Accelerating Cleanup: Paths to Closure Idaho Operations Office (DOE/EM0342, PLN-177; February) Idaho Falls, Idaho: U.S. Department of Energy Idaho Operations Office. Lodge, E. J. 1995. Settlement Agreement between Public Service Co. of Colorado v. Bart, No. CV 91-00350SOEIL (D. Id.) and United States v. Batt, No. CV-91-0054-S-EJL (D. Id.). Consent Order signed October 17, 1995, by Edward J. Lodge. Lopez, D. A., and R. R. Kimmitt. 1998. Vitrified Waste option Study Report (INEEL/EXT-97-01389; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. Lutze, W., and R. C. Ewing, eels. 1988. Radioactive Waste Forms for the Future. Amsterdam: North-Holland. Lutze, W. 1998. Candidate Waste Form(s) for INEEL Calcines. Presentation given at the National Research Council Committee's INEEL High-Level Waste Alternative Treatments Review meeting on October 1, at the Idaho Nuclear Technology and Engineering Center (INTEC). Idaho Falls, Idaho. Mann, N. R., and T. A. Todd. 1998. Evaluation and Testing of the Cells Unit Crossflow Filter on INEEL Dissolved Calcine Slurries (INEEL/EXT-98430749; August). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company. McDaniel, E. W., and D. B. Delzer. 1988. FUETAP Concrete. Pp. 565-588 in Radioactive Waste Forms for the Future, W. Lutze and R. C. Ewing, eds. Amsterdam: North-Holland. McNeese, L. E., J. B. Berry, G. E. Butterworth m, E. D. Collins, and T. H. Monk. 1988. Overall strategy and program plan for management of radioactively contaminated liquid wastes and transuranic sludges at the Oak Ridge National Laboratory (ORNL) (ORNL/TM-10757; December). Oak Ridge, TN: ORNL. Miller, C. J., A. L. Olson, and C. K. Johnson. 1997. Cesium absorption from acidic solutions using ammonium molybdophosphate on a polyacrylonitrile support (AMP-PAN). Separation Science and Technology. 32:14. Moore, J. G., H. W., Godbee, A. H. Kibbey, and D. S. Joy. 1975. Development of Cementitious Grouts for the Incorporation of Radioactive Wastes, Pan I: Leach Studies (ORNL-4962). Oak Ridge, Tenn.: Oak Ridge National Laboratory. Moore, J. G. 1981. A survey of concrete waste forms. Proceedings of a Conference on Alternative Nuclear Waste Forms and Interactions in Geologic Media (NTIS 194-216), J. G. Moore, L. A. Boatner ,and G. C. Battle, eels . Springfield, VA: National Technical Information Service. Murphy, J. A., L. Pincock, and I. N. Christiansen. 1995. ICPP Radioactive Liquid and Calcine Waste Technologies Evaluation Final Report and Recommendation (INEL-

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