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Technical Paper

The Accelerated Weathering of a Radioactive Low-Activity Waste Glass under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test

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Pages 149-165 | Published online: 10 Apr 2017

REFERENCES

  • F. M. MANN, “Annual Summary of ILAW Performance Assessmentfor 2002,” DOE/ORP-2000-19, Rev.1; CH2MHill Hanford Group, Inc. (2002).
  • Ecology; EPA; DOE Hanford Facility Agreement and Consent Order, As Amended, http://www.hanford.gov/tpa/tpahome.htm.
  • I. S. MULLER, A. C. BUECHELE, and I. L. PEGG, “Final Report: Glass Formulation and Testing with RPP-WTP-LAW Simulants,” VSL-01R3560-2, Vitreous State Laboratory, Catholic University of America (2001).
  • J. D. VIENNA, “Preliminary ILAW Formulation Algorithm Description,” 24590-LAW-RPT-RT-04-0003, Rev. 0; Bechtel National (2005).
  • B. P. McGRAIL, D. H. BACON, J. P. ICENHOWER, F. M. MANN, R. J. PUIGH, H. T. SCHAEF, and S. V. MATTIGOD, “Near-Field Performance Assessment for a Low-Activity Waste Glass Disposal System: Laboratory Testing to Modeling Results,” J. Nucl. Mater., 298, 95 (2001).
  • B. P. McGRAIL and D. H. BACON, “Selection of a Computer Code for Hanford Low-Level Waste Engineered-System Performance Assessment,” PNNL-10830, Rev. 1, Pacific North-west National Laboratory (1998).
  • B. P. McGRAIL, D. H. BACON, R. J. SERNE, and E. M. PIERCE, “A Strategy to Assess Performance of Selected Low-Activity Waste Forms in an Integrated Disposal Facility,” PNNL-14362, Pacific Northwest National Laboratory (2003).
  • B. P. McGRAIL, D. H. BACON, W. L. EBERT, and K. P. SARIPALLI, “A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford,” PNNL-11834, Rev. 1, Pacific Northwest National Laboratory (2000).
  • J. K. BATES and T. J. GERDING, “One-Year Results of the NNWSI Unsaturated Test Procedure: SRL 165 Glass Application,” ANL-85-41, Argonne National Laboratory (1986).
  • J. K. BATES, L. J. JARDINE, and M. J. STEINDLER, “Hydration Aging of Nuclear Waste Glass,” Science, 218, 51 (1982).
  • “Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT),” ASTM C1285, pp. 1-10, American Society for Testing and Materials (1994).
  • C. M. JANTZEN and N. E. BIBLER, “Product Consistency Test (PCT) for DWPF Glass: Part 1, Test Development and Protocol,” DPST-87-575, Savannah River Laboratory (1987).
  • J. K. BATES, J. W. EMERY, J. C. HOH, and T. R. JOHNSON, “Performance of High Plutonium-Containing Glasses for the Immobilization of Surplus Fissile Materials,” in Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries, V. JAIN and R. PALMER, Eds., Vol. 61, pp. 447–454, American Ceramic Society, Westerville, Ohio (1995).
  • B. P. McGRAIL, J. P. ICENHOWER, P. F. MARTIN, H. T. SCHAEF, M. J. O’HARA, E. A. RODRIGUEZ, and J. L. STEELE, “Waste Form Release Data Package for the 2001 Immobilized Low-Activity Waste Performance Assessment,” PNNL-13043, Rev. 2, Pacific Northwest National Laboratory (2001).
  • N. E. BIBLER, W. G. RAMSEY, T. F. MEAKER, and J. M. PAREIZS, “Durabilities and Microstructures of Radioactive Glasses for Immobilization of Excess Actinides at the Savannah River Site,” Proc. Material Research Symposium: Scientific Basis for Nuclear Waste Management XIX, Pittsburgh, Pennsylvania, November 27–December 1, 1995, Vol. 412, pp. 65–72,W. M. MURPHY and D. A. KNECHT, Eds., Materials Research Society (1996).
  • J. K. BATES, A. J. G. ELLISON, J. W. EMERY, and J. C. HOH, “Glass as a Waste Form for the Immobilization of Plutonium,” Proc. Materials Research Society Symposium: Scientific Basis for Nuclear Waste Management XIX, Pittsburgh, Pennsylvania, November 27–December 1, 1995, pp. 57–64,W. M. MURPHY and D. A. KNECHT, Eds., Materials Research Society (1996).
  • W. L. EBERT and J. K. BATES, “A Comparison of Glass Reaction at High and Low Glass Surface/Solution Volume,” Radioact. Waste Manage., 104, 372 (1993).
  • W. L. EBERT and S.-W. TAM, In “Dissolution Rates of DWPF Glasses from Long-Term PCT,” Materials Research Society Symposium: Scientific Basis for Nuclear Waste Management XX, Pittsburgh, Pennsylvania, December 2–6, 1996,W. J. GRAY and I. R. TRIAY, Eds., pp. 149–156, Materials Research Society (1997).
  • W. G. RAMSEY, N. E. BIBLER, and T. F. MEAKER, “Compositions and Durabilities of Glasses for Immobilization of Plutonium and Uranium,” Waste Management, Tucson, Arizona, February 26–March 2, 1995, pp. 23828–23907, Waste Management Symposia, Inc. (1995).
  • J. W. SHADE, and D. M. STRACHAN, “Effect of High Surface Area to Solution Volume Ratios on Waste Glass Leaching,” Ceramic Aware! Bull., 65, 12, 1568 (1986).
  • “High-Level Borosilicate Waste Glass: A Compendium of Corrosion Characteristics, Vol. 1,” DOE-EM-0177, U.S. Department of Energy Office of Waste Management (1994).
  • “High-Level Waste Borosilicate Glass: A Compendium of Corrosion Characteristics, Vol. 2,” DOE-EM-0177, U.S. Department of Energy Office of Waste Management (1994).
  • A. JIRICKA, J. D. VIENNA, P. R. HRMA, and D. M. STRACHAN, “The Effect of Experimental Conditions and Evaluation Techniques on the Alteration of Low Activity Glasses by Vapor Hydration,” J. Non-Crystal. Solids, 292, 1–3, 25 (2001).
  • B. P. McGRAIL, P. F. MARTIN, C. W. LINDENMEIER, and H. T. SCHAEF, “Application of the Pressurized Unsaturated Flow (PUF) Test for Accelerated Ageing of Waste Forms,” Proc. Int. Conf. Ageing Studies and Lifetime Extension of Materials, Oxford, United Kingdom, July 12–14, 1999.
  • C. L. CRAWFORD, D. M. FERRARA, R. F. SCHUMACHER, and N. E. BIBLER, “Crucible-Scale Active Vitrification Testing Envelope C, Tank 241-AN-102 (U),” WSRC-TR-2000-00371, SRT-RPP-2000-00022, Rev. 0, formerly BNF-003-98-0271, Westinghouse Savannah River Company (2001).
  • C. NASH, “Strontium-Transuranic Precipitation and Crossflow Filtration of 241-AN-102 Large C,” WSRC-TR-2000-00506, SRT-RPP-2001-00006, formerly BNF-03-98-0317, Westinghouse Savannah River Company (2000).
  • W. D. KING, N. M. HASSAN, and D. J. McCABE, “Intermediate-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102,” WSRC-TR-2000-00420, SRT-RPP-2000-00024, Westinghouse Savannah River Company (2000).
  • “Standard Test Methods for Sieve Analysis of Fine and Coarse Aggregates,” ASTM C136, pp. 1-10, American Society for Testing and Materials (2001).
  • B. P. McGRAIL, W. L. EBERT, A. J. BAKEL, and D. K. PEELER, “Measurement of Kinetic Rate Law Parameters on a Na-Ca-Al Borosilicate Glass for Low-Activity Waste,” J. Nucl. Mater., 249, 175 (1997).
  • B. P. McGRAIL, J. P. ICENHOWER, P. F. MARTIN, D. R. RECTOR, H. T. SCHAEF, E. A. RODRIGUEZ, and J. L. STEELE, “Low-Activity Waste Glass Studies: FY2000 Summary Report,” PNNL-13381, Pacific Northwest National Laboratory (2000).
  • D. WOLFF-BOENISCH, S. R. GISLASON, E. H. OELKERS, and C. PUTNIS, “The Dissolution Rates of Natural Glasses as a Function of Their Composition at pH 4 and 10.6, and Temperatures from 25 to 74°C,” Geochim. Cosmochim. Acta, 68, 23, 4843 (2004).
  • B. P. McGRAIL, P. F. MARTIN, H. T. SCHAEF, C. W. LINDENMEIER, and A. T. OWEN, “Glass/Ceramic Interactions in the Can-In-Canister Configuration for Disposal of Excess Weapons Plutonium,” Proc. Material Research Symposium: Scientific Basis for Nuclear Waste Management XXIII, Boston, Massachusetts, November 29–December 2, 1999, pp. 345–352,R. W. SMITH and D. W. SHOESMITH, Eds., Material Research Society (2000).
  • B. P. McGRAIL, C. W. LINDENMEIER, P. F. MARTIN, and G. W. GEE, “The Pressurized Unsaturated Flow (PUF) Test: A New Method for Engineered-Barrier Materials Evaluation,” in Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries II,V. JAIN and D. K. PEELER, Eds., Vol. 72, pp. 317–329, The American Ceramic Society, Westerville, Ohio (1996).
  • B. P. McGRAIL, C. W. LINDENMEIER, and P. F. MARTIN, “Characterization of Pore Structure and Hydraulic Property Alteration in Pressurized Unsaturated Flow Tests,” Proc. Material Research Symposium: Scientific Basis for Nuclear Waste Management, Warrendale, Pennsylvania, November 30–December 4, 1998, pp. 421–428,D. J. WRONKIEWICZ and J. H. LEE, Eds., Materials Research Society (1999).
  • P. J. WIERENGA, M. H. YOUNG, G. W. GEE, R. G. HILLS, C. T. KINCAID, T. J. NICHOLSON, and R. E. CADY, “Soil Characterization Methods for Unsaturated Low-Level Waste Sites,” PNL-8480, Pacific Northwest Laboratory (1993).
  • B. P. McGRAIL, J. P. ICENHOWER, D. H. BACON, J. D. VIENNA, K. P. SARIPALLI, H. T. SCHAEF, P. F. MARTIN, R. D. ORR, E. A. RODRIGUEZ, and J. L. STEELE, “Low-Activity Waste Glass Studies: FY2002 Summary Report,” PNNL-14145, Pacific Northwest National Laboratory (2002).
  • B. E. SCHEETZ, W. P. FREEBORN, D. K. SMITH, C. ANDERSON, and M. ZOLENSKY, “The Role of Boron in Monitoring the Leaching of Borosilicate Glass Waste Forms,” Proc. Material Research Society Symposium, Boston, Massachusetts, November 26–29, 1984, pp. 129–134, Materials Research Society (1985).
  • B. P. McGRAIL, P. F. MARTIN, and C. W. LINDENMEIER, “Accelerated Testing of Waste Forms Using a Novel Pressurized Unsaturated Flow Method,” Proc. Materials Research Society Symposium: Scientific Basis for Nuclear Waste Management XX, Pittsburgh, Pennsylvania, 1997, pp. 253–260, W. J. GRAY and I. R. TRIAY, Eds., Materials Research Society (1997).
  • E. M. PIERCE, B. P. McGRAIL, E. A. RODRIGUEZ, H. T. SCHAEF, K. P. SARIPALLI, R. J. SERNE, K. M. KRUPKA, P. F. MARTIN, S. R. BAUM, K. N. GEISZLER, L. R. REED, and W. J. SHAW, “Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment,” PNNL-14805, Pacific Northwest National Laboratory (2004).
  • J. L. CONCA and J. WRIGHT, “Hydrostratigraphy and Recharge Distribution from Direct Measurements of Hydraulic Conductivity Using the UFA Method,” PNL-9424, Pacific Northwest National Laboratory (1992).
  • A. P. GAMERDINGER and D. I. KAPLAN, “Application of a Continuous-Flow Centrifugation Method for Solute Transport in Disturbed, Unsaturated Sediments and Illustration of Mobile-Immobile Water,” Water Resour. Res., 36, 7, 1747 (2000).
  • T. J. WOLERY, “EQ3NR, A Computer Program for Geochemical Aqueous Speciation-Solubility Calculations: Theoretical Manual, User’s Guide, and Related Documentation (Version 7.0),” UCRL-MA-110662 PT III, pp. 1-246, Lawrence Livermore National Laboratory (1992).
  • E. M. PIERCE, B. P. McGRAIL, J. MARRA, P. F. MARTIN, B. W. AREY, and K. N. GEISZLER, “Accelerated Weathering of a High-Level and Pu-Bearing Lanthanide Borosilicate Waste Glass in a Can-In-Canister Configuration,” Appl. Geo-chem. (accepted for publication).
  • S. V. MATTIGOD, R. J. SERNE, B. P. McGRAIL, and V. L. LEGORE. In “Radionuclide Incorporation in Secondary Crystalline Minerals from Chemical Weathering of Waste Glasses,” Materials Research Society Symposium, Warrendale, Pennsylvania, November 26–29, 2001, pp. 597–606, Materials Research Society (2002).
  • S. V. MATTIGOD, R. J. SERNE, V. L. LEGORE, K. E. PARKER, R. D. ORR, D. E. McCREADY, and J. S. YOUNG, “Radionuclide Incorporation in Secondary Crystalline Minerals Resulting from Chemical Weathering of Selected Waste Glasses: Progress Report: Task kd.5b,” PNNL-14391, Pacific Northwest National Laboratory (2003).
  • F. CHEN, R. C. EWING, and S. B. CLARK, “The Gibbs Free Energies and Enthalpies of Formation of U6+ Phases: An Empirical Method of Prediction,” Am. Mineral., 84, 650 (1999).
  • K. M. KRUPKA, D. I. KAPLAN, S. V. MATTIGOD, and R. J. SERNE, “Understanding Variation in Partition Coefficient, Kd, Values: Volume II. Review of Geochemistry and Available Kd Values for Cadmium, Cesium, Chromium, Lead, Plutonium, Radon, Strontium, Thorium, Tritium (3H), and Uranium,” EPA-402-R-99-004B, Environmental ProtectionAgency (1999).
  • I. GRENTHE, J. FUGER, R. J. M. KONINGS, R. J. LEMIRE, A. B. MULLER, C. NGUYEN-TRUNG, and H. WANNER, Chemical Thermodynamics of Uranium, North-Holland/Elsevier, NewYork (1992).
  • B. S. HEMINGWAY, “Thermodynamic Properties of Selected Uranium Compounds and Aqueous Species at 298.15 K and 1 bar and at Higher Temperatures—Preliminary Models for the Origin of Coffinite Deposits,” Open-File Report 82619; pp. 1-90, U.S. Geological Survey (1982).
  • S. N. NGUYEN, R. J. SILVA, H. C. WEED, and J. E. J. ANDREWS, “Standard Gibbs Free Energies of Formation at the Temperature 303.15K of Four Uranyl Silicates: Soddyite, Uranophane, Sodium Boltwoodite, and Sodium Weeksite,” J. Chem. Thermodyn., 24, 359 (1992).
  • H. MOLL, G. GEIPEL, W. MATZ, G. BERNARD, and H. NITSCHE, “Solubility and Speciation of (UO2)2SiO4-2H2O in Aqueous Systems,” Radiochim. Acta, 74, 3 (1996).
  • I. PEREZ, I. CASAS, M. MARTIN, and J. BRUNO, “The Thermodynamics and Kinetics of Uranophane Dissolution in Bicarbonate Test Solutions,” Geochim. Cosmochim. Acta, 64, 4, 603 (2000).

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