A novel waste form for disposal of spent-nuclear-fuel reprocessing waste: A vitrifiable cement

Nuclear Technology

Volumn 125, Issue 1, 1999, Pages 93-103

  Gougar, Mary Lou Dunzik ^a   Scheetz, Barry E ^a   Siemer, Darryl D ^b  

^a PENNSYLVANIA STATE UNIVERSITY   (United States)

^b Lockheed Martin Idaho Technology Company   (United States)

Author keywords

Hot isostatically pressed style vitrification; Hydroceramic; Radioactive waste form

Indexed keywords

CALCITE; CEMENTS; CERAMIC MATERIALS; COMPRESSIVE STRENGTH; DIFFUSION IN SOLIDS; FLUORSPAR; GLASS; LEACHING; NUCLEAR FUEL REPROCESSING; QUARTZ; RADIOACTIVE WASTE DISPOSAL; SPENT FUELS;

GLASS CERAMICS; LEACH INDEX; REACTIVE SILICA; VERMICULITE;

RADIOACTIVE WASTE VITRIFICATION;

EID: 0032734568     PISSN: 00295450     EISSN: None     Source Type: Journal    
DOI: 10.13182/NT99-A2935     Document Type: Article

References (25)

1. D. D. SIEMER, "Hot Isostatically Pressed Concrete as a RadWaste Form," Ceramics Transactions, Cincinnati, Ohio, April 29-May 4, 1996, Vol. 61, p. 657, American Ceramic Society (1996).
2. National Academy of Sciences and National Academy of Engineering Panel, "Solidification of High-Level Radioactive Wastes," NUREG/CR-0085R, U.S. Nuclear Regulatory Agency (1979).
3. G. A. FAIRHALL and J. D. PALMER, "The Evaluation of the Properties of Immobilized Intermediate Level Wastes," Radioactive Waste Management and the Nuclear Fuel Cycle, Vol. 9 (1-3), p. 51 (1987).
4. L. E. BROWNELL, C. H. KINDLE, and T. L. THEIS, "Review of Literature Pertinent to the Aqueous Conversion of Radionuclides to Insoluble Silicates with Selected References and Bibliography," ARH-2731, Rev. 1973, Atlantic Richfield Hanford Company (1973).
5. W. L. EBERT, K. K. BATES, and W. L. BOURCIER, "The Hydration of Borosilicate Glass in Liquid Water and Steam at 200°C," Waste Management '91, Tucson, Arizona, February 24-28, 1991, Vol. 11, p. 205, University of Arizona (1991).
6. I. J. WINOGRAD, "Radioactive Waste Disposal in Thick Unsaturated Zones," Science, 212, 1457 (1981).
7. "Radioactive Wastes at the Hanford Reservation-A Technical Review," App. E, p. 205, National Academy of Sciences (1978).
8. E. J. BONANO, M. S. Y. CHU, S. H. CONRAD, and P. T. DICKMANN, "The Disposal of Orphan Wastes Using the Greater Confinement Disposal Facility," Waste Management '91, Tucson, Arizona, February 24-28, 1991, Vol. 1, p. 861, University of New Mexico (1991).
9. L. L. PRICE, "Disposal Configuration Options for Future Uses of Greater Confinement Disposal at the Nevada Test Site," SAND 94-2105, UC-721, Sandia National Laboratories (1994).
10. D. D. SIEMER, B. E. SCHEETZ, and M. L. D. GOUGAR, "Hot Isostatic Press (HIP) Vitrification of Radwaste Concretes," Proc. Scientific Basis For Nuclear Waste Management XIX, Boston, Massachusetts, November 27-December 1, 1995, Materials Research Society (1996).
11. D. D. SIEMER, D. M. ROY, M. W. GRUTZECK, M. L. D. COUGAR, and B. E. SCHEETZ, "PCT Tests of Hot Isostatically Pressed Zeolitic Concretes," Scientific Basis For Nuclear Waste Management XX, Boston, Massachusetts, December 1-5, 1996, Materials Research Society (1997).
12. J. DAVIDOVITS, "Ancient and Modern Concretes: What is the Real Difference?" Concr. Int., (Dec. 1987).
13. IMAOKA, Advances in Glass Technology, Part I, p. 149, Plenum Press, New York (1962).
14. L. D. HULETT, Jr., A. J. WEINBERGER, K. J. NORTHCUTT, and M. FERGUSON, "Chemical Species in Fly Ash from Coal-Burning Power Plants," Science, Vol. 210 (1980).
15. R. CHARAM, Handbook of Glass Technology, 3rd ed., Rev., Banaras, India (1956).
16. L. R. DOLE, G. C. ROGERS, M. T. MORGAN, D. P. STINTON, J. H. KESSLER, S. M. ROBINSON, and J. G. MOORE, "Cement-Based Radioactive Waste Hosts Formed Under Elevated Temperatures and Pressures (FUETAP Concretes) for Savannah River Plant, High-Level Defense Waste," ORNL/TM-8579, Oak Ridge National Laboratory (1983).
17. "Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-Term Test Procedure," ANSI/ANS-16.1-1986, American Nuclear Society (1986).
18. A. MUURINEN, J. RANTANEN, and R. OVASKAINEN, "Diffusivities of Cesium and Strontium in Concretes and in Mixtures of Sodium Bentonite and Crushed Rock," Proc. Scientific Basis for Nuclear Waste Management VIII, Boston, Massachusetts, November 26-29, 1984, p. 883, Materials Research Society (1985).
19. D. C. GRANT, E. E. SMELTZER, M. C. SKRIBA, J. C. CWYNAR, and L. R. EISENTATT, "Leachability of Cement Encapsulated West Valley Radwaste Streams," Proc. Scientific Basis for Nuclear Waste Management VIII, Boston, Massachusetts, November 26-29, 1984, p. 875, Materials Research Society (1985).
20. A. KUMAR, "Diffusion and Pore Structure Studies in Cementitious Materials," PhD Thesis, The Pennsylvania State University (1985).
21. "MCC-1 Static Leach Test," PNL-39990, DOE/TIC-11400, Pacific Northwest Laboratory (Sep. 1983).
22. CRC Handbook of Chemistry and Physics, 65th ed., R. C. WEAST, Ed., p. F-165, CRC Press, Inc., Boca Raton, Florida (1984).
23. R. M. BARRER, J. F. COLE, and H. STICHER, "Part V, Low Temperature Hydrothermal Transformations of Kaolinite,"J. Chem. Soc., 2775 (1968).
24. G. S. BARNEY, "Fixation of Radioactive Waste by Hydrothermal Reactions with Clays, Adv. Chem. Ser., 153, 109 (1975).
25. D. D. SIEMER, M. W. GRUTZECK, D. M. ROY, and B. E. SCHEETZ, "Zeolite Waste Forms Synthesized from Sodium Bearing Waste and Metakaolinite," Proc. Waste Management '98, Tucson, Arizona, March 1-5, 1998, University of Arizona (1998).