Uranium mineralogy and the geologic disposal of spent nuclear fuel

Reviews in Mineralogy and Geochemistry

Volumn 38, Issue , 1999, Pages 474-497

  Wronkiewicz, David J ^a   Buck, Edgar C ^b  

^a MISSOURI UNIVERSITY OF SCIENCE AND TECHNOLOGY   (United States)

^b ARGONNE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33750575004     PISSN: 15296466     EISSN: None     Source Type: Book Series    
DOI: None     Document Type: Article

References (88)

1. Ahn TM 1994 Long-term C-14 source term for a high-level waste repository. Waste Mgmt 14:393-408
2. Ahn TM 1996 Dry oxidation and fracture of LWR spent fuels. U.S. Nuclear Regulatory Commission Report NUREG-1565, 29 p
3. Bruno J, Sandino A 1989 The solubility of amorphous and crystalline schoepite in neutral to alkaline aqueous solutions. In Scientific Basis for Nuclear Waste Management XII. Lutze W, Ewing RC (Eds) Mater Res Soc Symp Proc 127:871-878
4. Bruno J, Casas I, Cera E, Ewing RC, Finch RJ, Werme LO 1995 The assessment of the long-term evolution of the spent nuclear fuel matrix by kinetic, thermodynamic and spectroscopic studies of uranium minerals. In Scientific Basis for Nuclear Waste Management XVIII, Part 1. Murakami R, Ewing RC (Eds) Mater Res Soc Symp Proc 353:633-639
5. Bruton CJ, Shaw HF 1988 Geochemical simulation of reaction between spent fuel waste form and J-13 water at 25°C and 90°C. In Scientific Basis for Nuclear Waste Management XI. Apted MJ, Westerman RE (Eds) Mater Res Soc Symp Proc 112:485-494
6. Buck EC, Wronkiewicz DJ, Finn PA, Bates JK 1997 A new uranyl oxide hydrate phase derived from spent fuel alteration. J Nucl Mater 249:70-76
7. Buck EC, Finch RJ, Finn PA, Bates JK 1998 Retention of neptunium in uranyl alteration phases formed during spent fuel corrosion. In Scientific Basis for Nuclear Waste Management XXI. McKinley IG, McCombie C (Eds) Mater Res Soc Symp Proc 506:87-94
8. 6+ phases formed during the oxidation of spent nuclear fuel. J Nucl Mater 245:1-9
9. Burns PC, Hill FC (1999) Implications of the synthesis and structure of the Sr analogue of curite. Can Mineral (in press)
10. Burns PC 1999 Cs boltwoodite obtained by ion exchange from single crystals: Implications for the radionuclide release in a nuclear repository. J Nucl Mater 265:218-223
11. Buscheck TA, Nitao JJ, Ramspott LD 1996 Localized dryout: An approach for managing the thermal-hydrological effects of decay heat at Yucca Mountain. In Scientific Basis for Nuclear Waste Management XIX. Murphy WM, Knecht DA (Eds) Mater Res Soc Symp Proc 412:715-722
12. Cantlon JE, Allen CR, Arendt JW, Brewer GD, Cohon JL, Cording EJ, Domenico PA, Langmuir D, McKetta JJ Jr, Price DL, Verink ED Jr, Wong JJ 1995 U.S. Nuclear Waste Technical Review Board, Report to the U.S. Congress and the Secretary of Energy, 1995 Findings and Recommendations, 53 p
13. Cesbron F, Ildefonse P, Sichere MC 1993 New mineralogical data on uranophane and β-uranophane; synthesis of uranophane. Mineral Mag 57:301-308
14. 8 formation in SIMFUEL oxidized in air at 250°C. J Nucl Mater 230:250-258
15. 2(s) dissolution under oxidizing conditions. In Scientific Basis for Nuclear Waste Management XX. Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 465:535-542
16. Diaz-Arocas P, Garcia-Serrano J 1997 Coprecipitation studies from SIMFUEL solutions in 5 m NaCl media. In Scientific Basis for Nuclear Waste Management XX. Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 456:543-548
17. Einziger RE, Thomas LE, Buchanan HC, Stout RB 1992 Oxidation of spent fuel in air at 175 to 195°C. In High Level Radioactive Waste Management, Proceedings of the Third International Conference. Am Nucl Soc, LaGrange Park, Illinois, p 1449-1457
18. Ewing RC 1993 The long-term performance of nuclear waste forms: Natural materials - three case studies. In Scientific Basis for Nuclear Waste Management XVI. Interrante CG, Pabalan RT (Eds) Mater Res Soc Symp Proc 294:559-568
19. Ewing RC, Weber WJ, Clinard FW Jr 1995 Radiation effects in nuclear waste forms for high-level radioactive waste. Progress in Nucl Energy 29:63-127
20. Fillmore DL, Bulmahn 1994 Characteristics of Department of Energy spent nuclear fuel. In Proc Topical Meeting on DOE Spent Nuclear Fuel, 1994, Am Nucl Soc, LaGrange Park, Illinois, p 313ff
21. 2 under oxidizing conditions from Shinkolobwe, Katanga, Zaire: A natural analogue for the corrosion of spent fuel. Radiochim Acta 52/53:395-401
22. Finch RJ, Ewing RC 1992 The corrosion of uraninite under oxidizing conditions. J Nucl Mater 190:133-156
23. Finch RJ, Ewing RC 1994 Formation, oxidation and alteration of ianthinite. In Scientific Basis for Nuclear Waste Management XVII. A Barkatt, RA Van Konynenburg (Eds) Mater Res Soc Symp Proc 333:625-630
24. Finch RJ, Suksi J, Rasilainen K, Ewing RC 1995 The long-term stability of becquerelite. In Scientific Basis for Nuclear Waste Management XVIII, Part 1. Murakami T, Ewing RC (Eds) Mater Res Soc Symp Proc 353:647-652
25. Finch RJ, Hawthorne FC, Ewing RC 1998 Structural relations among schoepite, metaschoepite, and "dehydrated schoepite." Can Mineral 36:831-845
26. 2 fuel in vapor and dripping groundwater at 90°C. In Scientific Basis for Nuclear Waste Management XXII. Wronkiewicz DJ, Lee JH (Eds) Mater Res Soc Symp Proc 556, (in press)
27. Finn PA, Buck EC, Gong M, Hoh JC, Hafenrichter LD, Bates JK 1994 Colloidal products and actinide species in leachate from spent nuclear fuel. Radiochim Acta 66/67:197-203
28. Finn PA, Buck EC, Hoh JC, Bates JK 1995 Spent fuel's behavior under dynamic drip tests. Global 1995, International Conference on Evaluating Emerging Nuclear Fuel Cycle Systems. Am Nucl Soc Topical Meeting. 241-248
29. Forsyth RS, Werme LO 1992 Spent fuel corrosion and dissolution. J Nucl Mater 190:3-19
30. Frondel C 1956 Mineral composition of gummite. Am Mineral 41:539-568
31. 2 matrix dissolution rates and grain boundary inventories of Cs, Sr, and Tc in spent LWR fuel. In Scientific Basis for Nuclear Waste Management XIV. Abrajano TA Jr, Johnson LH (Eds) Mater Res Soc Symp Proc 212:205-212
32. Gray WJ, Wilson CN 1995 Spent fuel dissolution studies FY1991 to FY 1994. Pacific Northwest Laboratory Report PNL-10540/UC-802, December 1995
33. Gray WJ 1999 Inventories of iodine-129 and cesium-137 in the gaps and grain boundaries of LWR spent fuels. In Scientific Basis for Nuclear Waste Management XXII. Wronkiewicz DJ, Lee LH (Eds) Mater Res Soc Symp Proc 556, (in press)
34. Harrar JE, Carley JF, Isherwood WF, Raber E 1990 Report of the committee to review the use of J-13 well water in Nevada nuclear waste storage investigations. Lawrence Livermore National Laboratory Report UCID-21867
35. Integrated Data Base Report - 1994 (1995) US Department of Energy Report DOE/RW-0006, Rev. 11
36. 2 fuel. Nucl Tech 63:470-475
37. Johnson LH, Shoesmith, DW 1988 Spent Fuel, Chapter 11, In Radioactive Waste Forms for the Future. Lutze W, Ewing RC (Eds) Elsevier, p. 635-698
38. Kansa EJ, Hanson BD, Stout RB 1999 Grain size and burnup dependence of spent fuel oxidation: Geological repository impact. In Scientific Basis for Nuclear Waste Management XXII. Wronkiewicz DJ, Lee JH (Eds) Mater Res Soc Symp Proc 556, (in press)
39. Kim CW, Wronkiewicz DJ 1999 Incorporation of radionuclides in the alteration phases of spent nuclear fuel. Migration '99, abstract (accepted)
40. Langmuir D 1978 Uranium solution-mineral equilibria at low temperatures with applications to sedimentary ore deposits. Geochim Cosmochim Acta 42:547-569
41. Leslie BW, Pearcy EC, Prikryl JD 1993 Oxidative alteration of uraninite at the Nopal I deposit, Mexico: Possible contaminant transport and source term constraints for the proposed repository at Yucca Mountain. In Scientific Basis for Nuclear Waste Management XVI. Interrante CG, Pabalan RT (Eds) Mater Res Soc Symp Proc 294:505-512
42. Louthan MR Jr, Iyer NC, Sindelar RL, Peacock HB Jr 1996 Disposal of aluminum based spent fuels in a repository. In Scientific Basis for Nuclear Waste Management XIX. Murphy WM, Knecht DA (Eds) Mater Res Soc Symp Proc 412:91-98
43. Matzke HJ, Spino J 1996 Formation of the rim structure in high burnup fuel. In Proc Int'l Workshop "Interfacial Effects in Quantum Engineering Systems." IEQES 96, Proc J Nucl Mater 18 p
44. McGillivray GW, Geeson DA, Greenwood RC 1994 Studies of the kinetics and mechanisms of the oxidation of uranium by dry and moist air. A model for determining the oxidation rate over a wide range of temperatures and water pressures. J Nucl Mater 208:81-97
45. 8 uranyl sheet. In Scientific Basis for Nuclear Waste Management XX. Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 465:581-588
46. Murphy WM, Pearcy EC 1992 Source-term constraints for the proposed repository at Yucca Mountain, Nevada, derived from the natural analog at Peña Blanca, Mexico. In Scientific Basis for Nuclear Waste Management XV. Sombret CG (Ed) Mater Res Soc Symp Proc 257:521-527
47. Murphy WM 1993 Geochemical models for gas-water-rock interactions in a proposed nuclear waste repository at Yucca Mountain, Nevada. In Site Characterization and Model Validation Focus ''93 Topical Meeting, Am Nucl Soc 115-121
48. Murphy WM 1995 Natural analogs for Yucca Mountain. Radwaste 2:44-50
49. Murphy WM 1997 Retrograde solubilities of source term phases. In Scientific Basis for Nuclear Waste Management XX Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 465:713-720
50. NRC 1995 Technical bases for Yucca Mountain standards. Committee on Technical Bases for Yucca Mountain Standards, National Research Council, National Academy Press, Washington DC, 222 p
51. NRC 1998 Electrometallurgical Techniques for DOE Spent Fuel Treatment: Spring 1998 Status Report on Argonne National Laboratory's R&D Activity. Committee on Electrometallurgical Techniques for DOE Spent Fuel Treatment, National Research Council, National Academy Press, Washington D.C. 78 p
52. Nguyen SN, Silva RJ, Weed HC, Andrews JRJ 1992 Standard Gibbs free energies of formation at 30°C of four uranyl silicates: Soddyite, uranophane, sodium boltwoodite and sodium weeksite. Chem Therm 24:259-276
53. Oversby VM 1994 Nuclear waste materials. In Materials Sciences and Technology A Comprehensive Treatment. Chan RW, Haasen P, Kramer EJ (Eds) VCH Verlagsgesellschaft, Germany
54. Pearcy EC, Prikryl JD, Murphy WM, Leslie BW 1994 Alteration of uraninite from the Nopal I deposit, Peña Blanca District, Chihuahua, Mexico, compared to degradation of spent nuclear fuel in the proposed U.S. high-level nuclear waste repository at Yucca Mountain, Nevada. Appl Geochem 9:713-732
55. Pickett DA, Murphy WM 1997 Isotopic constraints on radionuclide transport at Peña Blanca. In 7th CEC Natural Analogue Working Group Meeting Proc. von Maravic H, Smellie J (Eds) EUR 17851 EN, European Commission, Luxembourg, 113-122
56. Pickett DA, Murphy WM 1999 Unsaturated zone waters from the Nopal I natural analog. Chihuahua, Mexico - Implications for radionuclide mobility at Yucca Mountain. In Scientific Basis for Nuclear Waste Management XXII. Wronkiewicz DJ, Lee JH (Eds) Mater Res Soc Symp Proc 556, (in press)
57. Plyasunov AV, Grenthe I 1994 The temperature dependence of stability constants for the formation of polynuclear cationic complexes. Geochim Cosmochim Acta 58:3561-3582
58. Posey-Dowty J, Axtmann E, Crerar D, Borscik M, Ronk A, Woods W 1987 Dissolution rate of uraninite and uranium roll-front ores. Econ Geol 82:184-194
59. Sagüés, AA 1999 Nuclear waste package corrosion behavior in the proposed Yucca Mountain repository. In Scientific Basis for Nuclear Waste Management XXII Wronkiewicz DJ, Lee LH (Eds) Mater Res Soc Symp Proc 556 (in press)
60. 2O System: Transformation of schoepite into becquerelite and compreignacite. Radiochim Acta 66/67:37-43
61. SCP 1988 - Site Characterization Plan, U.S. Department of Energy, Office of Civilian Radioactive Waste Management, Report DOE/RW-0199
62. 2) dissolution rates under waste disposal conditions. J Nucl Mater 190:20-35
63. Shoesmith DW, Sunder S, Bailey MG, Miller NH 1996 Corrosion of used nuclear fuel in aqueous perchlorate and carbonate solutions. J Nucl Mater 227:287-299
64. Steward SA, Mones ET 1997 Comparison and modeling of aqueous dissolution rates of various uranium oxides. In Scientific Basis for Nuclear Waste Management XX Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 465:535-542
65. Stohl FV, Smith DK 1981 The crystal chemistry of the uranyl silicate minerals. Am Mineral 66:610-625
66. 99Tc in used CANDU fuels. In Scientific Basis for Nuclear Waste Management XVI. Interrante CG, Pabalan RT (Eds) Mater Res Soc Symp Proc 294:41-46
67. 129I in used CANDU fuels. In Scientific Basis for Nuclear Waste Management XVIII, Part 1. Murakami T, Ewing RC (Eds) Mater Res Soc Symp Proc 353:625-631
68. 2 fuel by the products of gamma radiolysis of water. J Nucl Mater 190:78-86
69. Sunder S, Shoesmith DW, Miller NH 1995 Prediction of the oxidative dissolution rates of used nuclear fuel in a geological disposal vault due to the alpha radiolysis of water. In Scientific Basis for Nuclear Waste Management XVIII, Part 1 Murakami T, Ewing RC eds.) Mater Res Soc Symp Proc 353:617-624
70. 2 pellet surfaces in air at 229 to 275°C. J Nucl Mater 88:153-160
71. 2: Calculations and observations. Nucl Tech 104:164-170
72. 2 fuel oxidized in air-steam mixtures at 225°C. J Nucl Mater 223:316-320
73. 2 fuel pellets under simulated disposal conditions. Nucl Chem Waste Mgmt 5:141-147
74. Thomas LE, Einziger RE, Woodley RE 1989 Microstructural examination of oxidized spent fuel PWR fuel by transmission electron microscopy. J Nucl Mater 166:243-251
75. Thomas LE, Charlot LA 1990 Analytical electron microscopy of light-water reactor fuels. Ceramic Trans 9:397-407
76. Thomas LE, Beyer CE, Charlot LA 1992 Microstructural analysis of LWR spent fuels at high burnup. J Nucl Mater 188:80-89
77. Thorstenson DC, Weeks EP, Haas H, Woodward JC 1989 Physical and chemical characteristics of topographically affected airflow in an open borehole at Yucca Mountain, Nevada, Nucl Waste Isol Unsat Zone. Focus '89, Am Nucl Soc 256-270
78. TSPA-VA 1998 Viability assessment of a repository at Yucca Mountain, Vol 3: Total system performance assessment, December 1998. U.S. Department of Energy Office of Civilian Radioactive Waste Management Report DOE/RW-0508/V3 (http://www.ymp.gov/vadoc/v3)
79. 8 into different uranium oxide hydrates. Mineral Petrol 41:247-255
80. Vochten R, van Haverbeke L 1990 Transformation of schoepite into the uranyl oxide hydrates: becquerelite, billietite and wölsendorfite. Mineral Petrol 43:65-72
81. Weber WJ, Turcotte RP, Roberts FP 1982 Radiation damage from alpha decay in ceramic nuclear waste forms. Radioactive Waste Mgmt 2:295-319
82. Weber WJ, Roberts FP 1983 A review of radiation effects in solid nuclear waste forms. Nucl Tech 60:178-198
83. Weber WJ, Ewing RC, Catlow CRA, Diaz de la Rubia T, Hobbs LW, Kinoshita C, Matzka Hj, Motta AT, Nastasi M, Salje EKH, Vance ER, Zinkle SJ 1998 Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium. J Mater Res 13:1434-1484
84. Wilson CN 1990 Results from NNWSI series 3 spent fuel tests. Pacific Northwest Laboratory Report PNL-7170/UC-802
85. 2 at 90°C. J Nucl Mater 190:107-127
86. 2 at 90°C: Implications for the corrosion of spent nuclear fuel. J Nucl Mater 238:78-95
87. 2 pellets. In Scientific Basis for Nuclear Waste Management XX. Gray WJ, Triay IR (Eds) Mater Res Soc Symp Proc 465:519-526
88. Wronkiewicz DJ, Bates JK, Buck EC, Hoh J, Emery J, Wang LM 1997b Radiation effects on moist-air systems and the influence of radiolylic product formation on nuclear waste glass corrosion. Argonne National Laboratory Report, ANL-97/15, 238 p