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.
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.
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.
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.
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.
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-
94/0119; April). Idaho Falls, Idaho: U.S. Department of Energy/Idaho National Engineering and Environmental Laboratory.
Murray, R. F., D. W. Rhodes. 1962. Low-Temperature Polymorphic Transformations of Calcined Alumina. (Phillips Petroleum Company Atomic Energy Division, Contract AT (10-1)-205. [TID-4500, Ed. 17. IDO-14581. September] Idaho Falls, Idaho: U.S. Atomic Energy Commission.
National Research Council (NRC). 1965. The Radiochemistry of Plutonium. NAS-NS 3058. G. H. Coleman. ed. Clearinghouse for Federal Scientific and Technical Information, National Bureau of Standards, U.S. Department of Commerce, Springfield, Virginia.
NRC. 1999. An End State Methodology for Identifying Technology Needs for Environmental Management, with an Example from the Hartford Site Tanks. Washington, D.C.: National Academy Press.
Newby, B. J., J. H. Valentine, G. L. Cogburn, and C. M. Slansky. 1978. Calcination Flowsheet Development. Allied Chemical Corporation (INEEL TID-4500, R65; October). Idaho Falls, Idaho: U.S. Department of Energy.
Oak Ridge National Laboratory (ORNL). 1996. Integrated Data Base Report—1995: U.S. Spent Nuclear Fuel and Radioactive Waste Inventories, Projections, and Characteristics . (DOE/RW-0006, Rev. 12- December). Washington, D.C.' U.S. Department of Energy.
ORNL. 1997. Integrated Data Base Report—1996: U.S. Spent Nuclear Fuel and Radioactive Waste Inventories, Projections, and Characteristics. (DOE/RW-0006, Rev. 13). Washington, D.C.: U.S. Department of Energy.
Office of Civilian Radioactive Waste Management. 1998. Civilian Radioactive Waste Management System Requirements Document Revision 4 (DOE/RW-0406, Rev4, May). Washington, D.C.: U.S. Department of Energy Office of Civilian Radioactive Waste Management.
Olson, A. L., W. W. Schulz, L. A. Burchfield, C. D. Carlson, J. L. Swanson, M. C. Thompson. 1993. Evaluation and Selection of Aqueous-Based Technology for Partitioning Radionuclides from ICPP Calcine (WlNCO-1171; February). Idaho Falls, Idaho: U.S. Department of Energy/Westinghouse Idaho Nuclear Company, Inc.
Olson, A. L. 1997. Planned Cs Removal Technology (ALO-02-97; interdepartmental communication). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Olson, A. L. 1998. Endstate Waste Form Requirements and Fates of Important Waste Constituents. Presentation given at the Idaho National Engineering and Environmental Laboratory (INEEL) Committee meeting on October 1-2, in Idaho Falls, Idaho.
Olson, A. L. 1998. Engineering Studies of Options. Presentation given at the INEEL Committee Meeting on August 18, at the Idaho Nuclear Technology and Engineering Center INTEC) in Idaho Falls, Idaho.
Olson, A. L., and C. Barnes. 1998. TRU Separations Options. Presentation given at the INEEL Committee Meeting on August 18, at the Idaho Nuclear Technology and Engineering Center (INTEC) in Idaho Falls, Idaho.
Olson, A. L., and D. Taylor. 1998. Hot Isostatic Press (HIP) Waste Option. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review on August 18, at the Idaho Nuclear Technology and Engineering Center (INTEC). Idaho Fails, Idaho.
Olson, A. L., and R. Kimmitt. 1998. Early Vitrification Option. Presentation given on August 18, at the NRC Committee's INEEL High-Level Waste Alternative Treatments
Review at the Idaho Nuclear Technology and Engineering Center (INTEC). Idaho Falls, Idaho.
Olson, A. L., and S. Losinski. 1998. Direct Cementitious Waste Option. Presentation given at the INEEL Committee Meeting on August 18, at the Idaho Nuclear Technology and Engineering Center in Idaho Falls, Idaho.
Organisation for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA). 1995. The Environmental and Ethical Basis of Geological Disposal of Long-Lived Radioactive Wastes. Paris, France: OECD NEA.
Oversby, V. M., C. C. McPheeters, C. Degueldre, and J. M. Paratte. 1997. Control of civilian plutonium inventories using burning in a non-fertile fuel. Journal of Nuclear Materials 245:12-26.
Palmer, W. B., M. J. Beer, M. Cukars, J. P. Law, C. B. Millet, J. A. Murphy, J. A. Nenni, C. V. Park, J. I. Pruitt, E. C. Thiel, F. S. Ward, and J. Woodard. 1994. ICPP Tank Farm Systems Analysis (WINCO-1192; January). Washington, DC: Westinghouse Idaho Nuclear Company, Inc.
Palmer, W. B. 1996. HLW Treatment Alternatives Evaluation (WBP-29-96 Draft Report; August 16). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Palmer, B. 1998. INTEC Waste Management. Presentation given at the 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.
Palmer, B. 1998. HLW Baseline Plan, Accelerating Cleanup: Paths to Closure. Presentation given at the National Research Council Committee's INEEL High-Level Waste Alternative Treatments Review meeting on August 17, at the INTEC. Idaho Falls, Idaho.
Palmer, B., and A. L. Olson. 1998. Sodium Beating Waste Treatment Study. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review meeting on August 17, at INTEC. Idaho Falls, Idaho.
Palmer, W. B., C. B. Millet, M. D. Staiger, and F. S. Ward. 1998. ICPP Tank Farm Planning through 2012 (INEEL/EXT-98-00339; April). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Parker, S. P. ed. 1994. Dictionary of Scientific and Technical Terms, Fifth Edition. New York McGraw-Hill.
Post, R. G. 1981. Independent Review Panel to Evaluate and Review Alternative Waste Forms to Immobilize the Idaho Chemical Processing Plant (ICPP) Calcined Waste, Final Report (ENICO-1088; December 1980). Idaho Falls, Idaho: U.S. Department of Energy Idaho Operations Office & ENICO.
Public Law (P. L.) 97425 (1982) as amended by P. L. 100-203 (1987) and P. L. 102486 (the Energy Policy Act of 1992).
Rawlins, J. K. 1998. Interim Storage Study Report (INEEL/EXT-97-01393; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Raytheon Engineers & Constructors. 1994. Idaho Chemical Processing Plant Waste Immobilization Facility Feasibility Study Report, October 1994, Volume I—Feasibility Design Description (MS511.163; October). Idaho Falls, Idaho: U.S. Department of Energy Idaho Operations Office.
Rebish, K. J. 1993. Letter (May) from K. J. Rebish of Idaho National Engineering Laboratory to B. H. O'Brien, Manager, Pilot Plant Support and Development regarding multiple linear regression of nitrate versus both sodium plus potassium and
excess calcium in selected pilot plant calcines. Idaho Falls, Idaho: U.S. Department of Energy.
Rechard, R., ed. 1995. Performance Assessment of the Direct Disposal in Unsaturated Tuff of Spent Nuclear Fuel and High-Level Waste Owned by U.S. Department of Energy, Volumes 1-3. Albuquerque, NM: Sandia National Laboratories.
Roberts, R., G. Choppin and J. Wild. 1986. The radiochemistry of uranium, neptunium and plutonium: an updating. Oak Ridge, Tenn.: Technical Information Center, Office of Scientific and Technical Information.
Ross, W. A., et al. 1983. Comparative leach testing of alternative transuranic waste forms. American Ceramic Society Bulletin. Pp. 1026-1035.
Russell, N. E., and A. D. Taylor. 1998. Hot Isostatic Press Waste Option Study Report (INEEL/EXT-97-01392; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Russell, N. E., T. G. McDonald, J. Banaee, C. M. Barnes, L. W. Fish, S. J. Losinski, H. K. Peterson, J. W. Sterbentz and D. R. Wenzel. 1998. Waste Disposal Options Report (INEEL/EXT-97-01145; February). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Sales, B. C., and L. A. Boatner. 1988. Lead-iron phosphate glass. Pp. 193-232 in Rach'oactive Waste Forms for the Future, W. Lutze and R. Ewing, eds. Amsterdam: North-Holland.
Schindler, R. E. 1974. Revised Design Criteria for ICPP Fourth Calcined Solids Storage Facility (September). Idaho Falls, Idaho: Allied Chemical Corporation, Idaho Chemical Programs, Operations Office.
Siemer, D. D., M. W. Grutzeck, and B. E. Scheetz. In Press. Paper on Comparison of Materials for Making Hydroceramic Waste Forms (abstract).
Siemer, D. D. 1995. Hot Isostatically Pressed Concrete as A Radwaste Form (abstract). Environmental Issues and Waste Management Technologies 61:657-664.
Siemer, D. D. 1995. Hot Isostatic Press (HIP) Vitrification of Radwaste Concretes. Pp. 403-410 in Materials Research Society Symposium Proceedings: Scientific Basis for Nuclear Waste Management XIX, Vol. 412. Boston, Mass.: Materials Research Society.
Siemer, D. D., D. M. Roy, M. W. Grutzeck, M. L. D. Gougar, and B. E. Scheetz. 1997. PCT Leach Tests of Hot Isostatically Pressed (HIPped) Zeolitic Concretes. Pp. 303-310 in Materials Research Society Symposium Proceedings: Scientific Basis for Nuclear Waste Management XX., Vol. 465. Boston, Mass.: Materials Research Society.
Siemer, D. D., M. W. Grutzeck, D. M. Roy, and B. E. Scheetz. 1998. Zeolite Waste Forms Synthesized From Sodium Bearing Waste and Metakaolinite. Waste Management '98. Session 36, Paper 2. Available at URL: http://www.wmsym.org/wm98/html/sess36/36-02/36-02.htm.
Slansky, C. M., ed. 1978. Technical Division Quarterly Progress Report October 1-December 1977, Idaho Chemical Programs (ICP-1141; February). Idaho Falls, Idaho: U.S. DOE/Allied Chemicals.
Slansky, C. M., B. R. Dickey, B. C. Musgrave, and R. L. Rohde. 1997. Technical Division Quarterly Progress Report July 1-September 30, 1997, Idaho Chemical Programs (ICP-1132; October). Idaho Falls, Idaho: U.S. Department of Energy/Allied Chemical.
Slaughterbeck, D. C., W. E. House, G. A. Freund, T. D. Enyeart, E. C. Benson, Jr., and K. D. Bulhman. 1995. Accident Assessments for Idaho National Engineering Laboratory Facilities. Science Applications International Corporation DOE/ID-10471. Idaho Falls, Idaho: U.S. Department of Energy.
Smith, H. D., E. O. Jones, A. J. Schmidt, A. H. Zacher, M. D. Brown, M. R. Elmore, and S. R. Gano. 1999. Denitration of High Nitrate Salts Using Reductants. Richland, Wash.: Pacific Northwest National Laboratory.
Sombret, C. 1998a. Letter (April 25) from C. Sombret to Tom Kiess of the National Research Council regarding some remarks about the fate of the INEEL calcined HLW. France.
Sombret, C. 1998b. E-mail (July 2) from C. Sombret to Tom Kiess of the National Research Council, regarding INEEL calcine. France.
Spaulding, B. C., R. A. Gavalya, M. M. Dahlmeir, L. C. Tuott, K. D. McAllister, K. C. DeCoria, S. P. Swanson, R. D. Adams, G. C. McCoy, R. J. Turk. 1998. ICCP Tank Farm Closure Study, Volumes I-III. Idaho Fails, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Staples, B. A., G. S. Pomiak, and E. L. Wade. 1979. Properties of Radioactive Calcine Retrieved from the Second Calcined Solids Storage Facility at ICPP: Idaho Chemical Programs (UC-70—ICP-1189; March). Idaho Falls, Idaho: U.S. Department of Energy/Allied Chemical Corporation.
Staples B., H. Cole, and D. Pavlica. 1983. Properties of formula 127 glass prepared with radioactive zirconia calcine, p. 125 in Scientific Basis for Nuclear Waste Management VI, ed. D. G. Brookins, Materials Research Society Symposium Proceedings V. 15. Elsevier Science Publishing Co., Inc.
Staples, B. A. 1994. Composition of Calcines from H3 Campaign of the NWCF. Letter (October) to J. D. Herzog, Supervisor HLW Immobilization, INEL, Idaho Falls, Idaho: U.S. Department of Energy.
Staples, B. A., T. P. O'Holleran, D. A. Knecht, P. C. Kong, S. J. Johnson, K. Vinjamuri, B. A. Scholes, A. W. Erickson, S. M. Frank, M. K. Meyer, M. Hansen, E. L. Wood, and H. C. Wood. 1997. Preparation of Plutonium Waste Forms with ICPP Calcined High-Level Waste (INEEL/EXT-97-00496). Idaho Falls, Idaho: U.S. DOE/Lockheed Martin Idaho Technologies Company.
Staples, B. 1998. Twenty Years of INTEC Waste Form Development. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review meeting on August 18, at the Idaho Nuclear Technology and Engineering Center INTEC). Idaho Falls, Idaho.
Staples, B. A., D. K. Peeler, G. F. Piepel, J. D. Vienna, B. A. Scholes, and C. A. Musick. 1998. The Preparation and Characterization of INTEC HAW Phase I Composition Variation Study Glasses (INEEL/EXT-98-009'/0; September). Idaho Fails, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
TFA (Tanks Focus Area). 1998. TFA Technical Highlights: Period Ending October 30, 1998. U.S. Department of Energy/Pacific Northwest National Laboratory.
TFA. 1999. TFA Technical Highlights: Period Ending January 31, 1999. U.S. Department of Energy/Pacific Northwest National Laboratory.
Technical Peer Review Team. 1994. Report of the Technical Peer Review of the Idaho Chemical Processing Plant High-Level Waste Treatment Program. Technical Peer Review. Idaho Falls, Idaho: U.S. Department of Energy/Westinghouse Idaho Nuclear Company, Inc.
Thompson, M. In Press. Pretreatment Radionuclide Separations of Cs/Tc from Supernates (Document No. WSR-MS-98-00601). Savannah, Ga.: U.S. Department of Energy/Westinghouse.
Todd, T. A., K. N. Brewer, D. J. Wood, P. A. Tullock, L. G. Olson, and A. L. Olson. In Press. Evaluation and testing of inorganic ion exchange sorbents for the removal of
Cesium-137 from Idaho Chemical Processing Plant Acidic Tank Waste. (abstract). Separation Science & Technology
Ullman, F., ed. 1985. Encyclopedia of Industrial Chemistry. Fifth Ed., 1st Rev., Vol. Al. VCH.
U.S. Department of Energy (U.S. DOE). 1985. An Evaluation of Commercial Repository Capacity for the Disposal of Defense High-Level Waste . Washington, D.C.: U.S. DOE.
U.S. DOE. 1987. Proposed Method for Assigning Metric Tons of Heavy Metal Values to Defense High-Level Waste Forms to be Disposed of in A Geologic Repository (DOE/RL-87-04 -August). Richland, WA: U.S. DOE.
U.S. DOE. 1996a. Waste Acceptance Criteria for the Waste Isolation Pilot Plant. Westinghouse Electric Corporation Nuclear Fuel Business Unit Waste Isolation Division. (DOE/WIPP-069 Revision 5; April). Washington, D.C.: DOE.
U.S. DOE. 1996b. Idaho National Engineering Laboratory Site Treatment Plan. (DOE/ID-10419; October). Idaho Falls, Idaho: U.S. DOE.
U.S. DOE. 1996c. Waste Acceptance Product Specifications (WAPS) For Vitrified High-Level Waste Forms EM-WAPS Rev. 02. U.S. DOE Office of Environmental Management.
U.S. DOE. 1997. Nevada Test Site Waste Acceptance Criteria (DOE/NV-335 NTSWAC, Revision 1; August). Reno, NV: U.S. DOE Nevada Operations Office Waste Management Division.
U.S. DOE Office of Environmental Management. 1997. Integrated Data Base Report-1996: U.S. Spent Nuclear Fuel and Radioactive Waste Inventories, Projections, and Characteristics. (DOE/RW-0006, Revision 13, December). Oak Ridge, Tenn.: Oak Ridge National Laboratory.
U.S. DOE. 1998a. FY1998 TFA Technical Midyear Review. Idaho Falls, Idaho: U.S. DOE Idaho Operations Office.
U.S. DOE Office of Environmental Management. 1998. Accelerating Cleanup: Paths to Closure (Draft. DOE/EM-0342; February). Washington, D.C.: U.S. DOE.
U.S. DOE. 1998b. Accelerating Clean up: Paths to Closure (DOE/EM-0362; June). Washington, D.C.: U.S. DOE Office of Environmental Management
U.S. DOE. 1998c. DOE Awards Contract. Environmental Update Summer (18).
U.S. DOE Alternatives Team. 1998. Process for Identifying Potential Alternatives for the INEEL High-Level Waste and Facilities Disposition Environmental Impact Statement (Predecisional Draft) DOE-ID 10627. Idaho Falls, Idaho: U.S. DOE.
Vinjamuri, K. 1991. Durability, Mechanical, and Thermal Properties of Experimental Glass-Ceramic Forms for Immobilizing ICPP High-Level Waste. High-Level Radioactive Waste Management. Proceedings of the Second International Conference Las Vegas, Nevada April 28-May 3, 1991.708-713
Vinjamuri, K., S. V. Raman, D. A. Knecht, and J. D. Herzog. 1992. Waste Form Development for Immobilization of High Level Waste Calcine at the Idaho Chemical Processing Plant. Proceedings of the Third International Conference Las Vegas, Nevada April 12-16, 1992, High Level Radioactive Waste Management 2:1261-1271.
Vinjamuri, K. 1994. Glass-ceramic waste forms for immobilization of the fluorinel-sodium, alumina, and zirconia calcines stored at the Idaho chemical processing plant. Ceramic Transactions 45:3-12.
Vinjamuri, K. 1994. Soil-Based Glass-Ceramic Waste Forms for Immobilization of the Fluorinel/Sodinm Calcined High-Level Waste Stored at the Idaho Chemical Processing Plant. Pp. 775-760 in Proceedings of the International Topical Meeting
on Nuclear and Hazardous Waste Management—Spectrum '94 August 14-18, 1994. Atlanta, Ga: American Nuclear Society.
Vinjamuri, K. 1994. Effect of aluminum and silicon reactants and hip soak time on characteristics of glass-ceramic waste forms. Ceramic Transactions 45:265-275.
Vinjamuri, K. 1995a. Glass Waste Forms for the Na-bearing High Activity Waste Fractions. INEL-95/0214; June). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Vinjamuri, K. 1995b. Candidate glass-ceramic waste forms for immobilization of the calcines stored at the Idaho chemical processing plant. Ceramic Transactions 61:439-446.
Wichmann, T., N. Brooks, and M. Heiser. 1996. Regulatory Analysis and Proposed Path Forward for the Idaho National Engineering Laboratory High-Level Waste Program. (DOE/ID-10544, Revision 1; October). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
Wichmann, T. 1998. High-Level Waste Regulatory Framework and Issues. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review meeting on August 18, at the Idaho Nuclear Technology and Engineering Center INTEC). Idaho Falls, Idaho.
Wichmann, T. 1998. NAS Regulatory Framework. Presentation given at the NRC Committee's INEEL High-Level Waste Alternative Treatments Review meeting on October 1-2, at the Idaho U.S. Department of Energy Operations Office. Idaho Falls, Idaho.
Winograd, I. J. 1981. Radioactive Waste Disposal in Thick Unsaturated Zones. Science 212(4502):1457-1464.
Wood, D. J., J. D. Law, T. G. Gain, R. D. Tillotson, P. A. Tullock, and T. A. Todd. 1997. Development of the SREX Process for the Treatment of ICPP Liquid Wastes (INEEL/EXT-97/00831; October). Idaho Falls, Idaho: U.S. Department of Energy/Lockheed Martin Idaho Technologies Company.
