Nuclear Waste Vitrification in the United States: Recent Developments and Future Options
Source abstract
Abstract
Nuclear power plays a key role in maintaining current worldwide energy growth while minimizing the greenhouse gas emissions. A disposition path for used nuclear fuel (UNF) must be found for this technology to achieve its promise. One likely option is to recycle UNF and immobilize the high‐level waste (HLW) by vitrification. Vitrification is the technology of choice for immobilizing HLW from defense and commercial fuel reprocessing around the world. Recent advances in both recycling technology and vitrification show great promise in closing the U.S. nuclear fuel cycle in an efficient fashion. This article summarizes the recent trends, developments, and future options in waste vitrification for both defense waste cleanup and closing the nuclear fuel cycle in the United States.
Source: crossref · Quality: baseline
Research context
OpenAlex topics: Radioactive element chemistry and processing · Nuclear materials and radiation effects · Nuclear and radioactivity studies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (100+)
Show source-provided references
1. Solomon S. · 2007
2. W. F.MartinandJ.Ahearne eds. “Nuclear Energy: Policies and Technology for the 21st Century ”Report of the Nuclear Energy Advisory Committee to U.S. Secretary of Energy Washington DC 2008.
3. Laidler J. J. · 2008 · 695
4. Todd T. A. · 2006 · 41
5. Nuclear Waste Glasses
6. Review
7. Ojovan M. I. · 2008 · 245
8. Vitrification of Toxic Wastes
9. Steering Committee on Vitrification of Radioactive Wastes. “National Research Council Glass as a Waste Form and Vitrification Technology ”Summary of an International Workshop National Academy of Sciences Press Washington DC 1996.
10. Caurant D. · 2009
11. Ojovan M. I. · 2007
12. 10.1002/978144431935410.1002/9781444319354 ↗
13. 10.2172/714377710.2172/7143777 ↗
14. R.Bonniaud C.Sombret andD.Rancon “Vitrification of Fission Products Concentrated Solutions: Technological Studies ”Symposium on Treatment and Storage of High‐Level Radioactive Waste IAEA Vienna Austria 1962.
15. W. F.Hamel M. J.Sheridan andP. J.Valenti “Vitrification at the West Valley Demonstration Project ”Radiowaste Magazine 27–40 1988.
16. 10.2172/532586710.2172/5325867 ↗
17. S.Naline V.Robineau F.Gouyaud C.Girold andB.Carpentier “Vitrification 2010—A Challenging French Vitrification Project to Retrofit a Cold Crucible Inductive Melter at the La Hague Plant ”Waste Management 2010 10382 Phoenix AZ 2010.
18. Abrigo G. P. · 1995
19. Smith G. L. · 1996
20. J.Fleisch W.Gruenewald G.Roth E.Schwaab W.Tobie andN.Weishaupt “Cold Test Operation of the German VEK Vitrification Plant ”Waste Management'08 8326 Phoenix AZ 2008.
21. Vitrification of Radioactive Waste by High‐frequency Inductive Melting in a Cold Crucible
22. Radioactive Wastes Vitrification Using Induction Cold Crucible Melter
23. The Vitrified Solution
24. A.Bonnetier J. F.Hollebecque J.Lacombe R. D.Quang andP.Rivat “Development of an Advanced Cold Crucible for Direct Induction Melting of Glass ”Proceedings of the 4th International Conference on Electromagnetic Processing of Materials Lyon France 2003.
25. 10.2172/96572210.2172/965722 ↗
26. D. M.Miles V.Gotovchikov N.Gurvitch J. A.Etheridge R.Arun‐Kumar andW. G.Ramsey “Installation of the Hybrid Plasma Induction Cold Crucible Melter ”1999 International Conference on Incineration and Thermal Treatment Technologies Orlando FL 1999.
27. T. D.ChikallaandJ. A.Powell Nuclear Waste Management Semiannual Progress Report October 1981 through March 1982 PNL‐4250‐1 Pacific Northwest Laboratory Richland WA 1982.10.2172/6058024 ↗
28. T. D.ChikallaandJ. A.Powell Nuclear Waste Management Semiannual Progress Report April 1982 through September 1982 PNL‐4250‐2 Pacific Northwest Laboratory Richland WA 1982.10.2172/6058024 ↗
29. 10.2172/726615510.2172/7266155 ↗
30. J.Powell et al “AVS: Experimental Tests of a New Process to Inductively Vitrify HLW inside the Final Disposal Containers at Very High Waste Loadings ” inWaste Management'02 Tucson AZ 2002.
31. Stir‐Melter™ Vitrification of Simulated Radioactive Waste, Fiber Glass Scrap, and Municipal Waste Combustor Fly Ash
32. Rapid Stirred Melting of Simulated West Valley High Level Waste
33. Oxy‐Gas‐Fired Submerged Combustion Melter
34. 10.2172/3527510.2172/35275 ↗
35. Sturcken E. F. · 1991
36. Woskov P. P. · 2007
37. 10.2172/1012307110.2172/10123071 ↗
38. 10.2172/20234910.2172/202349 ↗
39. Ahearne J. · 2001
40. Brinko A. J. · 2003
41. International Atomic Energy Agency (IAEA) · 2009
42. Bradley D. J. · 1997
43. 10.2172/80561610.2172/805616 ↗
44. 10.2172/94110810.2172/941108 ↗
45. 10.1016/S0022-3093(03)00010-310.1016/S0022-3093(03)00010-3 ↗
46. Relationship Between Liquidus Temperature and Solubility
47. 10.1023/A:102108112616210.1023/A:1021081126162 ↗
48. 10.1016/S0022-3093(01)00874-210.1016/S0022-3093(01)00874-2 ↗
49. Liquidus Temperature Limited Waste Loading Maximization for Vitrified HLW
50. Glass Formulation for INEEL Sodium Bearing Waste
51. 10.1016/S0022-3093(01)00875-410.1016/S0022-3093(01)00875-4 ↗
52. 10.2172/1500116210.2172/15001162 ↗
53. Aloy A. · 2006
54. Sulfate Retention during Waste Glass Melting
55. 10.2172/89325710.2172/893257 ↗
56. Hrma P. · 2003 · 147
57. Darab J. G. · 2001
58. Pegg I. L. · 2000
59. Sulfate Retention and Segregation in Simulated Radioactive Waste Borosilicate Glass
60. Matlack K. S. · 2009
61. 10.2172/91510910.2172/915109 ↗
62. 10.2172/82404010.2172/824040 ↗
63. Revisiting the SO4 Limit for the Defense Waste Processing Facility10.1002/9781118407950.ch21 ↗
64. Raszewski F. C. · 2008
65. 10.2172/94110810.2172/941108 ↗
66. Effect of Crystallization on the Chemical Durability of Simulated Nuclear Waste Glasses
67. 10.2172/93880010.2172/938800 ↗
68. Kim D. S. · 2008
69. Corrosion of Partially Crystallized Glasses
70. Effects of Al2O3, B2O3, Na2O, and SiO2 on Nepheline Formation in Borosilicate Glasses
71. Effect of Crystallization on High‐Level Waste Glass Corrosion10.1002/9781118371435.ch25 ↗
72. H.Li Y. L.Chen andJ. D.Vienna “Phase Separation in Borosilicate Glasses with P F S and the Influence on Glass Durability in Aqueous Environments ”Plutonium Futures – the Science Conference Transactions LA‐13338‐C Los Alamos National Laboratory Los Alamos NM 113–114 (1997).
73. Matlack K. S. · 2007
74. 10.1016/j.jnoncrysol.2006.02.05110.1016/j.jnoncrysol.2006.02.051 ↗
75. Li H. · 1997 · 261
76. Plaisted T. · 2000 · 709
77. Glass Formulation for Idaho National Engineering and Environmental Laboratory Zirconia High‐Activity Waste
78. Vienna J. D. · 1999
79. Crum J. V. · 1997 · 79
80. Hrma P. · 2001
81. Schill P. · 2001
82. J.Matyas Description of the Behavior of Multitude Particles in Non‐isothermal Convective Melting Space PhD. Thesis Laboratory of Inorganic Materials Prague Czech Republic 2001.
83. J.Matyas J.Klouzžek L.Nemec andM.Trochta “Spinel Settling in HLW Melters ”ICEM'01 The 8th International Conference On Radioactive Waste Management and Environmental Remediation Bruges Belgium 2001.10.1115/ICEM2001-1317 ↗
84. 10.1002/9780470930991.ch510.1002/9780470930991.ch5 ↗
85. Fox K. M. · 2007
86. Matlack K. S. · 2009
87. Evaluation of Crystallinity Constraint for HLW Glass Processing
88. Edwards T. B. · 2006
89. Fox K. M. · 2006
90. 10.2172/91510810.2172/915108 ↗
91. Relationship Between Liquidus Temperature and Solubility
92. 10.2172/88277210.2172/882772 ↗
93. J. S.McCloyandJ. D.Vienna Glass Composition Constraint Recommendations for Use in Life‐Cycle Mission Modeling. PNNL‐19372 Pacific Northwest National Laboratory Richland WA 2010.10.2172/978973 ↗
94. 10.1016/S0022-3115(03)00325-810.1016/S0022-3115(03)00325-8 ↗
95. Iron Phosphate Glass for Immobilization of Hanford LAW
96. 10.1016/S0956-053X(99)00331-110.1016/S0956-053X(99)00331-1 ↗
97. 10.1016/S0022-3093(99)00631-610.1016/S0022-3093(99)00631-6 ↗
98. Iron Phosphate Glasses
99. 10.2172/1500364610.2172/15003646 ↗
100. 10.1016/j.jnoncrysol.2003.08.07010.1016/j.jnoncrysol.2003.08.070 ↗