Abstract
Glass and polycrystalline materials for high-level radioactive waste immobilization are discussed. Borosilicate glass has been selected as the waste form for defence high-level radwaste in the US. Since release of the radionuclides to the biosphere is the major concern, this paper focuses on the potential interactions between the waste form and its surroundings. In addition to laboratory data, results from field testing are also presented in order to provide a comprehensive overview of glass leaching under near repository-like conditions.
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G. K. Ortel andR. D. Walton, Jr, in “Advances in Ceramics”, Vol. 9, edited by G. G. Wicks and W. A. Ross (American Ceramics Society, Columbus, Ohio, 1984) p. 1.
Engineered Waste Package System Design Specification ONWI-423 (Battelle Columbus Laboratories, Columbus, Ohio, 1983).
M. J. Smith, Engineered Barrier Development for a Nuclear Waste Repository Located in Basalt: An Integration of Curret Knowledge, RHO-BWI-ST0-7 (Rockwell Hanford Operations, Richland, Washington, 1980).
Interim Reference Repository Conditions for a Nuclear Waste Repository in Basalt, Report No. NWTS-16 (Office of Nuclear Waste Isolation Columbus, Ohio, 1981).
M. J. Plodinec, G. G. Wicks andN. E. Bibler, An Assessment of Savannah River Borosilicate Glass in the Repository Environment, DP-1629 (Savannah River Laboratory, Aiken, South Carolina, 1982).
J. E. Mendel,Nucl. Technol. 32 (1977) 72.
W. Lutze (ed), “Scientific Basis for Nuclear Waste Management V”, MRS Symposia Proceedings Vol. 11, (Elsevier, New York, 1982) p. 1.
B. Grambow andW. Lutze, in “Scientific Basis for Nuclear Waste Management”, Vol. 2, edited by C. J. M. Northrup Jr (Plenum Press, New York, 1980) p. 109.
L. C. Watson, A. M. Aiken andA. R. Bancroft, Disposal of Radioactive Wastes, STI/PUB/18 (IAEA, Vienna, 1960) p. 379.
G. J. McCarty andM. T. Davidson,Ceram. Bull. 54 (1975) 782.
A. E. Ringwood, S. E. Kesson, N. G. Ware, W. Hibberson andA. Major,Nature 278 (1979) 219.
J. G. Moore, G. C. Rogers, S. Katz, M. T. Morgan andE. Newman, in “Waste Management '81”, Vol. I (University of Arizona, Tucson, Arizona, 1981) p. 267.
T. A. Bernadzikowski (ed), The Evaluation and Selection of Candidate High Level Waste Forms, USDOE/TIC-11611 (National Technical Information Service, Springfield, Virginia 22161, 1982).
L. L. Hench, D. E. Clark andJ. Campbell,Nucl. Chem. Waste Managemt. 5 (1984) 149.
CEA Group Anon., Radioactive Glasses: Research and Testing, (Editions MSA, 20 rue Therese, 75001 Paris, 1982) p. 269.
C. Sombret, R. Bonniard andA. Jovani, in Proceedings of the Conference on High Level Radioactive Solid Waste Forms, edited by L. A. Casey (US Nuclear Reg. Comm., Washington, DC, 1979).
J. B. Dunson, A. M. Eisenberg, R. L. Schuyler, T. H. Gould, J. L. Butler andJ. B. Pickett, Assessment of Processes, Facilities and Costs for Alternative Solid Forms for Immobilization of SRP Defence Waste, DP-1625 (Savannah River Laboratory, Aiken, South Carolina, 1982).
G. G. Wicks,Nucl. Technol. 55 (1981) 601.
R. E. DeWames, L. F. Grantham, J. Guon andR. L. McKisson, in Proceedings of 2nd International Symposium on Ceramics in Nuclear Waste Management (American Ceramic Society, Columbus, Ohio, 1983).
C. M. Jantzen, D. F. Bickford andD. G. Karraker, in Proceedings of 2nd International Symposium on Ceramics in Nuclear Waste Management (American Ceramic Society, Columbus, Ohio, 1983).
A State-of-the-Art Review of Materials Properties of Nuclear Waste Forms PNL-3802 (Battelle Pacific Northwest Laboratory, Richland, Washington, 1981).
M. J. Plodinec, P. D. Soper, N. E. Bibler andJ. L. Kessler, SRP Radioactive Glass Studies: SmallScale Process Development and Product Performance, DP-MS-82-26 (Savannah River Laboratory, Aiken, South Carolina, 1982).
Materials Characterization Center Test Methods, preliminary version, PNL-3940 (Pacific Northwest Laboratory, Richland, Washington 1980).
A. A. Hench andL. L. Hench,J. Nucl. Chem. Waste Managemt. 4(4) (1983) 231.
D. M. Strachan, in “Scientific Basis for Nuclear Waste Management, V”, edited by W. Lutze (Elsevier, New York, 1982) p. 181.
T. L. Nogues, L. L. Hench andJ. Zarzycki, in “Scientific Basis for Nuclear Waste Management”, edited by W. Lutze (Elsevier, New York, 1982) p. 211.
G. G. Wicks et al., paper presented at the Symposium on Scientific Basis for Nuclear Waste Management, Boston, Massachusetts, November 1984.
D. D. Walker, J. R. Wiley, M. D. Dukes andJ. H. Leroy, SRL Report (Savannah River Laboratory, Aiken, South Carolina 29808, 1980).
D. M. Strachan, in “Advances in Ceramics” Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramics Society, Columbus, Ohio, 1984) p. 12.
E. C. Ethridge, D. E. Clark andL. L. Hench,Phys. Chem. Glasses 10(2) (1979) 35.
G. L. McVay andC. O. Buckwalter, The Effect of Iron on Waste Glass Leaching, PNL-SA-10474 (Pacific Northwest Laboratory, Richland, Washington, 1982).
G. G. Wicks, B. M. Robnett andW. E. Rankin, in “Scientific Basis for Nuclear Waste Management”, Vol. V, edited by W. Lutze (Elsevier, New York, 1982) p. 15.
P. G. Coles et al., paper presented at the ACS Symposium Series 100, Radioactive Waste in Geologic Storage (American Chemical Society, Washington, DC, 1978).
D. M. Strachan, B. O. Barnes andR. P. Turcotte, in “Scientific Basis for Nuclear Waste Management”, Vol. 3, edited by J. G. Moore (Plenum Press, New York, 1981) p. 347.
R. B. Adiga, E. P. Akomer andD. E. Clark, paper presented at the Symposium on Scientific Basis for Nuclear Waste Management, Boston, Massachusetts, November, 1984, in “Scientific Basis for Nuclear Waste Management” Vol VIII, edited by C. M. Jantzen, I. A. Stone and R. C. Ewing (MRS, Pittsburgh, Pennsylvania, 1985) p. 45.
Wallace, private communication, 1984.
R. B.Adiga, thesis submitted to the University of Florida (1984).
G. L. McVay andC. O. Buckwalter, The Effect of Iron on Waste Glass Leaching, PNL-4A-10474 (Pacific Northwest Laboratory, Richland, Washington, 1982).
C. M. Jantzen, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross, (American Ceramic Society, Columbus, Ohio, 1984) p. 385.
Idem, in “Scientific Basis for Nuclear Waste Management”, edited by G. M. McVay (North-Holland, New York, 1984) p. 613.
Idem, paper presented at the American Ceramics Society Annual Meeting of Pittsburgh, May 1984.
A. Manara, F. Lanza, G. Della Mea, C. Rossi andG. Salvagno, in “Scientific Basis for Nuclear Waste Management, VII”, edited by G. M. McVay (North-Holland, New York, 1984) p. 735.
C. T. Lee andD. E. Clark, paper presented at the Symposium on Scientific Basis for Nuclear Waste Management, Boston, Massachusetts, November 1984, in “Scientific Basis for Nuclear Waste Management” Vol VIII, edited by C. M. Jantzen, I. A. Stone and R. C. Ewing (MRS, Pittsburgh, Pennsylvania, 1985) p. 221.
J. E. Mendel, Final Report of the Defence High Level Waste Leaching Mechanisms Program, PNL-5157/UC-70 (Battelle Pacific Northwest Laboratory, Richland, Washington 1984).
A. Paul,J. Mater. Sci. 12 (1977) 2246.
R. G. Newton andA. Paul,Glass Technol. 21(6) (1980) 307.
M. J. Plodinec, C. M. Jantzen andG. G. Wicks, in “Advances in Ceramics” Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 491.
L. L. Hench andA. R. Jurgensen, in preparation.
B. Grambow, paper presented at the Symposium on Scientific Basis for Nuclear Waste Management, Boston, Massachusetts, November 1984, in “Scientific Basis for Nuclear Waste Management” Vol VIII, edited by C. M. Jantzen, I. A. Stone and R. C., Ewing (MRS, Pittsburgh, Pennsylvania, (1985) p. 15.
N. E. Bibler, in “Scientific Basis for Nuclear Waste Management”, Vol. 6, edited by Stephen V. Topp (Elsevier, New York, 1982) p. 681.
J. A. Kelly, Evaluation of Glass as a Matrix for Solidification of Savannah River Plant Waste, Radioactive Studies, DP-1397 (Savannah River Laboratory, Aiken, South Carolina, 1975).
D. D. Walker, M. D. Dukes, M. J. Plodinec andN. E. Bibler, paper presented at the 181st National Meeting of the American Chemical Society, Atlanta, Georgia, March/April 1981.
G. L. McVay andL. R. Pederson,J. Amer. Ceram. Soc. 64(3) (1981) 154.
D. E. Clark, C. J. Pantano andL. L. Hench, “Glass Corrosion” (Glass Industry, Books for Industry, New York, 1979).
R. P. Turcotte, J. W. Wald, F. P. Roberts, J. M. Rusin andW. Lutze,J. Amer. Ceram. Soc. 65(12) (1982) 589.
W. J. Weber, in “Scientific Basis for Nuclear Waste Management, VI”, edited by D. G. Brookins (Elsevier, New York, 1983) p. 407.
G. Malow, J. A. C. Marples andC. Sombret, in Proceedings of the First European Community Conference on Radioactive Waste Management Disposal, edited by P. Simon and S. Orlowski (Harwood Academic Publishers, Chur, Switzerland, 1980) p. 341.
R. P. Turcotte andJ. W. Wald, Devitrification Behavior in a Zinc Borosilicate Nuclear Waste Glass, PNL-2247 (Pacific Northwest Laboratory, Richland, Washington, 1978).
W. A. Ross, D. J. Bradley, L. R. Bunnell, W. J. Gray, Y. B. Katayama, G. B. Mellinger, J. E. Mendel, F. P. Roberts, R. P. Turcotte, J. W. Wald, W. E. Weber andJ. H. Westsik, Jr, Annual Report on the Characteriztion of High-Level Waste Glasses, PNL-2625 (Battelle Pacific Northwest Laboratory, Richland, Washington, 1978).
C. M. Jantzen, D. F. Bickford andD. G. Karraker, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus. Ohio, 1984) p. 30.
Ross, private communication (1975).
David Martin, private communication (1983).
Jarine, private communication (1981).
B. Grambow, in “Scientific Basis for Nuclear Waste Management, V”, edited by W. Lutze (Elsevier, New York, 1982).
L. P. Hatch, edited byAmer. Scientist 41 (1953) 410.
G. J. McCarthy,J. Mater. Sci. 8 (1973) 1358.
G. J. McCarthy andM. T. Davidson,Amer. Ceram. Soc. Bull. 54 (1975) 782.
G. J. McCarthy,Trans. Amer. Nucl. Soc. 23 (1976) 168.
R. Roy,Amer. Ceram. Soc. Bull. 54 (1975) 459.
R. O. Schwoebel,ibid. 54 (1975) 459.
A. E. Ringwood, in “Safe Disposal of High-Level Nuclear Reactor Wastes: A New Strategy” (ANU Press, Canberra, Australia, 1978).
A. E. Ringwood, S. E. Kesson, N. G. Ware, W. O. Hibberson andA. Major,Geochem. J. 13 (1979) 141.
S. E. Kesson andA. E. Ringwood,Mater. Res. Symp. Proc. 26 (1984) 507.
P. E. D. Morgan, D. R. Clarke, C. M. Jantzen andA. B. Harker,J. Amer. Ceram. Soc. 64 (1981) 249.
A. B. Harker, C. M. Jantzen, P. E. D. Morgan andD. R. Clarke, in “Scientific Basis for Nuclear Waste Management”, Vol. 3 (Plenum, New York, 1981) p. 139.
A. B. Harker, P. E. D. Morgan, D. R. Clarke andJ. Flintoff,Mater. Res. Soc. Symp. Proc. 6 (1982) 567.
A. B. Harker, P. E. D. Morgan, J. Flintoff andD. R. Clarke, in Proceedings of the ANS Topical Meeting on the Treatment and Handling of Radioactive Wastes, Richland, Washington (1982) p. 335.
P. E. D. Morgan, A. B. Harker, J. F. Flinoff, T. M. Shaw andD. R. Clarke, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 234.
F. J. Ryerson, K. Burr andR. Rozsa, Formulation of Synroc-D Additives for Savannah River Plant HighLevel Radioactive Waste, UCRL-53237 (Lawrence Livermore National Laboratory, Livermore, California, 1981).
J. H. Campbell, F. J. Ryerson, R. B. Rozsa andC. L. Hoenig, Flexibility in Formulating and Processing Synroc-D: A Current Assessment, UCRL-87349 (Lawrence Livermore National Laboratory, Livermore, California, 1982).
J. Campbell, C. Hoenig, F. Bazan, F. Ryerson, M. Guinan, R. Van Konynenburg andR. Roza, Properties of Synroc-D Nuclear Waste Form: A State-of-the-Art Review, UCRL-53240 (Lawrence Livermore National Laboratory, Livermore, California, 1982).
R. J. Ryerson,J. Amer. Ceram. Soc. 67 (1984) 75.
A. B. Harker, Development of Polyphase Ceramics for the Immobilization of High-Level Defence Nuclear Waste, DOE Report DOE/ET/41900-18 on Contract DE-AC09-79ET41900 (Rockwell International Energy Systems Group, Canoga Park, California, 1983).
K. D. Reeve, D. M. Levins, J. L. Woolfrey andE. J. Ramm, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 200.
R. A. Spuanzini andP. J. Hayward, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 273.
P. J. Hayward, E. R. Vance, C. D. Cann andS. L. Mitchell, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 282.
A. B. Harker, P. E. D. Morgan andJ. Flintoff,J. Amer. Ceram. Soc. 67(2) (1984) C-26.
A. B. Harker andJ. F. Flintoff,Mater. Res. Soc. Symp. Proc. 26 (1984) 513.
Idem, “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 222.
P. E. D. Morgan, T. M. Shaw andE. A. Pugar, in “Waste Management '83”, Vol. 2, edited by R. G. Post (University of Arizona, Tucson, Arizona, 1983) p. 207.
Idem, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 209.
A. B. Harker, D. R. Clarke, C. M. Jantzen andP. E. D. Morgan, in “Surfaces and Interfaces in Ceramic and Ceramic-Metal Systems”, edited by J. Pask and A. Evans (Plenum, New York, 1981) p. 207.
D. R. Clarke,J. Amer. Ceram. Soc. 64(6) (1981) C-89.
C. M. Jantzen, D. R. Clarke, P. E. D. Morgan andA. B. Harker,ibid. 65(6) (1982) 292.
R. B. Rozsa andJ. H. Campbell, Disposal Costs for SRP High-Level Wastes in Borosilicate Glass and Crystalline Ceramic Waste Forms, UCRL-53315 (Lawrence Livermore National Laboratory, Livermore, California, 1982).
R. R. DeWames, R. L. McKisson, J. Guon andL. F. Grantham, in “Waste Management '83”, Vol. 2, edited by R. G. Post (University of Arizona, Tucson, Arizona, 1983).
R. E. DeWames, L. F. Grantham, J. Guon andR. L. McKisson, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 652.
R. W. McKee, P. M. Daling andL. E. Wiles, in “Advance in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, 1984) p. 666.
B. A. Staples, G. S. Pomiak andE. L. Wade, Properties of Radioactive Retrieved from the Second Calined Solids Storage Facility at ICPP, ICP-1189 (Idaho Chemical Processing Plant, Idaho Falls, Idaho, 1979).
J. A. Stone, J. A. Kelley andT. S. McMillan, Sampling and Analysis of SRP High-Level Waste Sludges, DP-1399 (Savannah River Laboratory, Aiken, South Carolina, 1976).
T. A. Bernadzikowski, J. S. Allender, J. A. Stone, D. E. Gordon, T. H. Gould Jr andC. F. Wesberry III,Ceram. Bull. 62 (1983) 1364.
P. E. D. Morgan andE. H. Cirlin,J. Amer. Ceram. Soc. 65 (1982) C-114.
P. E. D. Morgan andF. J. Ryerson,J. Mater. Sci. Lett. 1 (1982) 351.
D. R. Clarke andJ. F. Flinoff,Mater. Res. Soc. Symp. Proc. 15 (1983) 29.
A. B. Harker, W. B. White, C. G. Pantano andW. P. Freeborn, Leaching Mechanisms in Polyphase Ceramic High-Level Nuclear Waste Forms, PNL-5157 (Pacific Northwest Laboratory, Richland, Washington, 1984).
L. F. Grantham, R. L. McKisson, J. Guon, J. F. Flintoff andD. E. McKinzie, Process Description and Plant Design for Ceramic High-Level Waste Forms, DOE/ET/41900-16 (Rockwell International Energy Systems Group, Canoga Park, California, 1983).
L. F. Grantham, R. L. McKisson, R. E. DeWames, J. Guon, J. F. Flintoff andD. E. McKenzie, in “Waste Management '83”, Vol. 2, edited by R. G. Post (University of Arizona, Tucson, Arizona, 1983) p. 213.
F. J. Ackerman, J. Z. Grens, F. J. Ryerson, C. L. Hoenig, F. Bazan, P. E. Peters, R. Smith andJ. H. Campbell, Fluid-Bed Process for Synroc Production, UCRL-53405 (Lawrence Livermore National Laboratory, Livermore, California, 1983).
J. H. Campbell, R. B. Rozsa andC. L. Hoenig, Immobilization of High-Level Defence Wastes in Synroc-D: Recent R & D Results on Process Scale-up, UCRL-86558 (Lawrence Livermore National Laboratory, Livermore, California, 1983).
F. J. Ackerman, J. Z. Grens, F. J. Ryerson, C. L. Hoenig, F. Bazan andJ. H. Campbell, Synroc Production Using a Fluidized-Bed Calciner, UCRL-87742 (Lawrence Livermore National Laboratory, Livermore, California, 1982).
A. B. Harker andJ. F. Flintoff,J. Amer. Ceram. Soc. 68 (1985) 159.
Idem, Development of Reduced Volume Forms from Immobilizing ICCP Waste, SC5400-7FR (Rockwell International Science Center, Thousand Oaks, California, 1984).
L. L. Hench andL. Urwongse, “Evaluation of Five Glasses and a Glass-Ceramic for Solidification of Swedish Nuclear Waste”, SKBF/KBS Technical Report No. 80-22 (1980).
A. Alkiewicz, J. E. Gale, R. Thorpe andB. Paulsson, Geology and Fracture System at Stripa, Lawrence Berkeley Lab Report 8907 and subsequent Stripa Series LBL 7049, etc. (1979).
L. L. Hench, L. Werme andA. Lodding, in “Scientific Basis for Nuclear Waste Management”, Vol. 5, edited by W. Lutze (Elsevier, New York, 1982) p. 153.
L. Werme, L. L. Hench andA. Lodding,ibid.in p. 135.
L. L. Hench, A. Lodding andL. Werme, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 310.
D. E. Clark, B. F. Zhu, R. S. Robinson andG. G. Wicks, in “Advances in Ceramics”, Vol. 8, edited by G. G. Wicks and W. A. Ross (American Ceramic Society, Columbus, Ohio, 1984) p. 325.
L. L. Hench, D. B. Spilman andA. D. Buonaquisti,J. Nucl. Chem. Waste Managemt. 5 (1984) 75.
L. L. Hench, delivered at meeting on US-DOE Leaching Mechanisms Programme and its Relationship to Overall Defence High-Level Waste Management Effort, September, 1984, Germantown, Maryland.
L. L. Hench, A. Lodding andL. Werme,J. Nucl. Mater. 125 (1984) 273.
A. Lodding, L. L. Hench andL. Werme,ibid. 125 (1984) 280.
L. L. Hench, L. Werme andA. Lodding,ibid. in press.
B. F. Zhu, D. E. Clark, L. L. Hench andG. G. Wicks,J. Non-Cryst. Solids in press.
D. E. Clark, B. F. Zhu andL. L. Hench,Rivista Staz. Sper. Vetto 5 (1984) 185.
L. L. Hench andM. R. Wilson,J. Nucl. Mater. in press.
H. Cheung, L. L. Edwards andT. F. Harvey, Nuclear Waste-Form Risk Assessment for U.S. Defence Waste at Savannah River Plant, Annual Report FY 1982, AUCRL-53188-82 (Lawrence Livermore Laboratory, Livermore, California 1982).
L. L. Hench,J. Phys. Colloque C9 43 (1982) 625.
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Hench, L.L., Clark, D.E. & Harker, A.B. Nuclear waste solids. J Mater Sci 21, 1457–1478 (1986). https://doi.org/10.1007/BF01114698
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DOI: https://doi.org/10.1007/BF01114698