A US perspective on fast reactor fuel fabrication technology and experience. Part II: Ceramic fuels

Journal of Nuclear Materials

Volumn 393, Issue 1, 2009, Pages 1-11

  Burkes, Douglas E ^a   Fielding, Randall S ^a   Porter, Douglas L ^a   Meyer, Mitchell K ^a   Makenas, Bruce J ^b  

^a IDAHO NATIONAL LABORATORY   (United States)

^b Fluor Hanford   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CERAMIC FUELS; FUEL FABRICATIONS; FUEL TYPES; NATIONAL LABORATORY; NUCLEAR FUEL FABRICATION; POLICY MAKERS; REACTOR FUELS;

CARBIDES; FAST REACTORS; NITRIDES; NUCLEAR FUELS; RESEARCH; TECHNOLOGY;

FABRICATION;

EID: 68049094096     PISSN: 00223115     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jnucmat.2009.04.023     Document Type: Article

References (64)

1. US Department of Energy, A Technology Roadmap for Generation IV Nuclear Energy Systems, Issued by the Nuclear Energy Research Advisory Committee and the Generation IV International Forum, 2002.
2. US Department of Energy, Office of Nuclear Energy, Science and Technology, The US Generation IV Implementation Strategy, 2003.
3. US Department of Energy, Report to Congress on the Advanced Fuel Cycle Initiative, 2003.
4. US Department of Energy, Press Release, Department of Energy Announces New Nuclear Initiative, 2006.
5. B.R.T. Frost, P.G. Mardon, L.E. Russell, Research on the fabrication, properties, and irradiation behavior of plutonium fuels for the UK, in: Reactor Programme, Proceedings of the American Nuclear Society Meeting on Plutonium as a Power Reactor Fuel, Richland, WA, 1962, p. 4.1.
6. J.P. Mustelier, Quelques Resultes d'Irradiation Sur les Combustibles Evisages par Rapsodie, in: Symposium on the Effects of Iraddiation on Solids and Materials for Reactors, Venice, Italy, 1962, p. 163.
7. Kittel J.H., Frost B.R.T., Mustellier J.P., Bagley K.Q., Crittenden G.C., and van Dievoet J. J. Nucl. Mater. 204 (1993) 1
8. Boltax A. Mixed oxide fuel pin performance. In: Cahn R.W., Haasen P., and Kramer E.J. (Eds). Materials Science and Technology, A Comprehensive Treatment (1994), VCH Publishers Inc., New York 339
9. M. Mignanelli, P.E. Potter, in: Proceedings of the BNES Conference, Science and Technology of Fast Reactors, vol. 1, London, UK, 1986, p. 53.
10. Mignanelli M., and Potter P.E. Thermochim. Acta 129 (1988) 143
11. Strain R.V., Bottcher J.H., Ukai S., and Arii Y. J. Nucl. Mater. 204 (1993) 252
12. Leggett R.D., and Walters L.C. J. Nucl. Mater. 204 (1993) 23
13. Baker R.B., Bard F.E., Leggett R.D., and Pitner A.L. J. Nucl. Mater. 204 (1993) 109
14. Baker R.B., Bard F.E., and Ethridge J.L. Performance of Fast Flux Test Facility Driver and Prototype Driver Fuels, WHC-SA-0974-FP (1990), Westinghouse Hanford Company, Richland, WA p. 184
15. Williams J.F., and Rice L.H. Trans. ANS 34 (1980) 221
16. J.W. Hales, R.B. Baker, Evaluation of FFTF reference driver fuel to 100 MWd/kgM burnup, in: Proceedings of LMR: A Decade of LMR Progress and Promise, Washington, DC, 1990, p. 2-12.
17. L.A. Lawrence, S.M. Jensen, J.W. Hales, R.A. Karnesky, B.J. Makenas, Performance of advanced oxide fuel pins in EBR-II, in: ANS International Conference on Reliable Fuels for Liquid Metal Reactors, Tucson, AZ, 1986, p. 3-62.
18. In: Stoller S.M., and Richards R.B. (Eds). Reactor Handbook (1961), Interscience Publishers, Inc., New York 146
19. In: Wilson P.D. (Ed). The Nuclear Fuel Cycle-From Ore to Waste (1996), Oxford University Press, Oxford
20. H.W. Alter, J.K. Davidson, R.S. Miller, J.L. Mewherter, Process of making a neutronic reactor fuel element composition, US Patent 2868707, 1959.
21. Mulford R.N.R., and Ellinger F.H. J. Am. Chem. Soc. 80 (1958) 2023
22. Kincaid L., Aitken E., and Taylor I. Trans. Am. Nucl. Soc. 33 (1979) 176
23. National Academy of Sciences, Management and Disposition of Excess Weapons Plutonium - Reactor Related Options, National Academies Press, Washington, DC, 1995.
24. Belgian Tests Easing Gallium Out of MOX, Nucl. Europe Worldscan, vols. 1 and 2, 1998, p. 68.
25. S. Greene, Reactor-based Plutonium Disposition: Opportunities, Options, and Issues, MOX Fuel Cycle Technologies for Medium and Long Term Deployment (Proceedings of the Symposium Vienna, 1999), C&S Papers Series No. 3/p, IAEA, Vienna, 2000, p. 478 (CD-ROM).
26. H. Bairiot, J. Van Vliet, G. Chiarelli, Overview of MOX Fuel Fabrication Achievements, MOX Fuel Cycle Technologies for Medium and Long Term Deployment (Proceedings of the Symposium Vienna, 1999), C&S Papers Series No. 3/p, IAEA, Vienna, 2000, p. 81 (CD-ROM).
27. Harvey M.R., Teter A.R., and Leggett R.L. RFP-1255 (1969), Dow Chemical Co., Rocky Flats Division
28. Russell L.E., Brett N.H., Harrison J.D.L., and Williams J. J. Nucl. Mater. 5 2 (1962) 216
29. Biancheria A., and Allio R.J. Nucleonics 23 (1965) 46
30. F.W. Van Der Brugghen, M.E.A. Hermans, J.B.W. Kanji, A.J. Noothout, T. Van Der Plas, H.S.G. Slooten, Sol-gel processes for the preparation of spherical thorium-containing fuel particles, in: Proceedings of the Second International Thorium Fuel Cycle Symposium, Gatlinburg, TN, CONF-660524, 1968, p. 377.
31. S.D. Clinton, P.A. Haas, L.J. Hirth, Process for Preparing Oxide Gel Microspheres from Sols, US Patent 3290122, 1964.
32. RG. Wymer, Laboratory and Engineering Studies of Sol-gel Processes at Oak Ridge National Laboratory, ORNL-TM-2205, 1968.
33. Nelson R.L., Parkinson N., and Kent W.C.L. Nucl. Tech. 53 (1981) 196
34. Ringle H.D., and Zimmer E. Nucl. Tech. 45 (1979) 28
35. Zimmer E., Ganguly C., Borchardt J., and Langen H. J. Nucl. Mater. 152 (1988) 169
36. Matthews R.B., and Hart P.E. J. Nucl. Mater. 92 (1980) 207
37. Lambert J.D.B., and Strain R. Oxide fuels. In: Cahn R.W., Haasen P., and Kramer E.J. (Eds). Materials Science and Technology, A Comprehensive Treatment (1994), VCH Publishers Inc., New York 111
38. 2 High Burnup Program, GEAP-3108, General Electric, 1959.
39. J.M. Steffen, J.L. Manuel, M.A. Coffman, Fabrication Data for the HEDL P-44 Improved Oxide Fuel Test Fuel Pins, TC-1771, Hanford Engineering Development Laboratory, 1990.
40. S.L. Hayes, M.K. Meyer, D.C. Crawford, G.S. Chang, F.W. Ingram, Irradiation testing of actinide transmutation fuels in the advanced test reactor, in: Proceedings of AccApp/ADTTA-01, American Nuclear Society, 2001.
41. Blank H. J. Nucl. Mater. 153 (1988) 171
42. A.A. Bauer, P. Cybulskis, R.L. Petty, N.S. Demuth, in: Proceedings of the International Conference on Fast Breeder Reactor Fuel Performance, Monterrey, CA, 1979.
43. Matthews R.B., and Herbst R.J. Nucl. Tech. 63 (1983) 9
44. R.J. Herbst, R.W. Stratton, LMR advanced fuels - (U, Pu)-carbide fabrication, performance and reliability, in: ANS International Conference on Reliable Fuels for Liquid Metal Reactors, Tucson, AZ, 1986, p. 7-1.
45. Mason R.E., Hoth C.W., Stratton R.W., and Botta F. Trans. Am. Nucl. Soc. 66 (1992) 215
46. Stratton R.W., Ledergerber G., Ingold F., Latimer T.W., and Chidester K.M. J. Nucl. Mater. 204 (1993) 39
47. Frost B.R.T. J. Nucl. Mater. 10 4 (1963) 265
48. Matthews R.B., Chidester K.M., Hoth C.W., Mason R.E., and Petty R.L. J. Nucl. Mater. 151 (1988) 334
49. C.M. Cox, D.S. Dutt, R.A. Karnesky, in: Proceedings of the First Symposium on Space Nuclear Power Systems, Albuquerque, NM, vol. 2, 1984, p. 301.
50. R.B. Matthews, Transactions of the Seventh Symposium on Space Nuclear Power Systems, Albuquerque, NM, CONF-900109, 1990.
51. J.W. Hales, B.J. Makenas, D.S. Dutt, SP-100 fuel pin irradiation testing, in: Transactions Sixth Symposium on Space Nuclear Power Systems, Albuquerque, NM, 1989.
52. W.F. Lyon, R.B. Baker, R.D. Leggett, R.B. Matthews, in: Proceedings International Conference on Fast Reactors and Related Fuel Cycles, Kyoto, Japan, 1991.
53. H.J. Matzke, Science of Advanced LMFBR Fuels, Elsevier Science Publishers, New York, NY, 1986 (Chapter 10).
54. W.F. Lyon, R.B. Baker, R.D. Leggett, R.B. Matthews, WHC-SA-1067, Westinghouse Hanford Company, 1991.
55. Muromura T., and Tagawa H. J. Nucl. Mater. 71 (1977) 65
56. Muromura T., and Tagawa H. J. Nucl. Mater. 80 (1979) 330
57. Oetting F.L., and Leitnaker J.M. J. Chem. Thermodyn. 4 (1972) 199
58. Evans P.E. J. Nucl. Mater. 10 1 (1963) 43
59. Chiotti P. J. Am. Ceram. Soc. 35 5 (1952) 123
60. V.J. Tennery, T.G. Godfrey, R.A. Potter, Synthesis, Characterization and Fabrication of UN, ORNL-4608, Oak Ridge National Laboratory, 1970.
61. Rundle R.E., Baenziger N.C., Wilson A.S., and McDonald R.A. J. Am. Chem. Soc. 70 (1948) 99
62. J.Y. Chang, Hot Pressing Study on Mixed Uranium-Plutonium Nitride for Advanced Reactor Fuel, ORNL-5051, Oak Ridge National Laboratory, 1975.
63. Anselin F. J. Nucl. Mater. 10 (1963) 301
64. Tennery V.J., Godfrey T.G., and Potter R.A. J. Am. Ceram. Soc. 54 (1971) 327