Induced nuclear reactions: processes – systems – and elements – Fuel component structure – Encased with nonfuel component
Reexamination Certificate
2011-07-12
2011-07-12
Palabrica, Rick (Department: 3663)
Induced nuclear reactions: processes, systems, and elements
Fuel component structure
Encased with nonfuel component
C376S421000, C376S409000
Reexamination Certificate
active
07978808
ABSTRACT:
A nuclear fuel element including a uranium-molybdenum alloy that provides an enhanced reactivity in research, test and radioisotope production nuclear reactors. In this uranium-molybdenum alloy, the uranium is enriched in the isotope 235-U, while the molybdenum is depleted in the isotope 95-Mo. The thus obtained enhanced reactivity provides, depending on the exact use of the fuel element, a requirement for less uranium in the fuel and the use of the fuel elements during a longer period in the reactor.
REFERENCES:
patent: 2772964 (1956-12-01), Thomas et al.
patent: 2926113 (1960-02-01), McGeary et al.
patent: 3266890 (1966-08-01), Greenspan et al.
patent: 3306733 (1967-02-01), Virot et al.
patent: 3343947 (1967-09-01), Fizzotti et al.
patent: 3407116 (1968-10-01), Clough
patent: 3790440 (1974-02-01), Keshishian
patent: 3979498 (1976-09-01), Campbell
patent: 4064025 (1977-12-01), Chen
patent: 4140910 (1979-02-01), Kroon
patent: 4162231 (1979-07-01), Horwitz et al.
patent: 4193855 (1980-03-01), Tuccio
patent: 4363970 (1982-12-01), Allan et al.
patent: 4381286 (1983-04-01), Floreancig
patent: 4389292 (1983-06-01), Phillips et al.
patent: 4447303 (1984-05-01), Jensen et al.
patent: 4568436 (1986-02-01), Feichtner et al.
patent: 4584184 (1986-04-01), Nalewajek et al.
patent: 4690742 (1987-09-01), Cantrell et al.
patent: 4705577 (1987-11-01), Ondracek
patent: 4818477 (1989-04-01), Chubb
patent: 4963317 (1990-10-01), Wiencek et al.
patent: 5082603 (1992-01-01), Horie et al.
patent: 5250231 (1993-10-01), Grossman et al.
patent: 5393322 (1995-02-01), Ugo
patent: 5978432 (1999-11-01), Kim et al.
patent: 6140522 (2000-10-01), Mol et al.
patent: 7187744 (2007-03-01), Mol et al.
patent: 2002/0149125 (2002-10-01), Gradel et al.
patent: 2003/0223530 (2003-12-01), Mol et al.
patent: 001345239 (2003-09-01), None
patent: 1186004 (1970-04-01), None
patent: 766 061 (1957-01-01), None
Hofman et al. “Initial Assessment of Radiation Behavior of Very-High-Densit Low-Enriched-Uranium Fuels.” International Meeting on Reduced Enrichment for Reasearch and Test Reactors (RERTR). Budapest, Hungary. Oct. 3-8, 1999. pp. 0-14.
Tennery et al. “Radiological environment assessment of the recycle of LMFBR advanced fuels.” International Meeing on Advanced LMFBR Fuels. Tucson, AZ. Oct. 10, 1977. pp. 1-21.
Porta et al. “Core severe accidents with cermet fuels—a specific study for pressurized water reactors.” Journal of Nuclear Materials. 274 (1999). pp. 174-180).
Neeft et al. “Post irradiation examinatino of uranium inclusions in inert matrices.” Progress in Nuclear Energy. vol. 38, No. 3-4, pp. 427-430, 2001.
Wiencek et al. “Low-Enriched Uranium-Molybdenum Fuel Plate Development.” 2000 International Meeting on Reduced Enrichment for Research and Test Reactors. Oct. 1-6, 2000, Las Vegas, Nevada, USA. pp. 0-11.
Verrall et al. “Silicon carbide as an inert-matrix for a thermal reactor fuel.” Journal of Nuclear Materials. 274 (1999) 54-60.
Vettraino et al. “Preliminary Fabrication and characterization of inert matrix and thoria fuels for plutonium disposition in light water reactors.” Journal of Nuclear Materials. 274 (1999) 23-33.
Bakker et al., “Using molybdenum depleted in 95 Mo in UMo fuel”, The 24 Internat. Meeting RERTR , Santa Clara, Argentina, on Nov. 3-8, 2002.
Hofman et al. “Initial Assessment of Radiation Behavior of Very-High-Density Low-Enriched-Uranium Fuels.” International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Budapest, Hungary. Oct. 3-8, 1999. pp. 0-14.
Cowan et al., “Optimizing BWR water Chemistry Sixth Internat. Symp. On Environmental Degradation of Metals in Nuclear Power Systems- Water Reactors”, pp. 889-894, 1993.
Bretscher et al. “Neutronic feasibility studies using U-Mo dispersion Fuel for LEU conversion of the Maria, IR-8 and WWR-SM research reactors.” 2000 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Las Vegas, Nevada, 2000.
Conn et al. “Minimizing Radioactivity and other Features of Elemental and Isotopic Tailoring of Materials for Fusion Reactors”, UWFDM-305; Nuclear Technology, 41, 389, 1978.
Greenwood et al., “Production of 91-Nb, 94-Nb, and 95-Nb from Mo by 14.5-14.6 MeV neutrons”, Physical Review C, vol. 35, No. 1, Jan. 1987, pp. 76-80.
Bretscher, et al., Neutronic Feasibility Studies Using U-Mo Dispersion Fuel (9 Wt% Mo, 5.0 gU/cc) for LEU Conversion of the Maria (Poland), IR-8 (Russia), and WWR-SM (Uzbekistan) Research Reactors, 2000 International Meetingon Reduced Enrichment for Research and Test Reactors, Oct. 1-6, 2000, Nevada, pp. 1-14.
Bakker, et al., “Using molybdenum depleted in 95-Mo in UMo fuel”, 2002 International Meeting on Reduced Enrichment for Research and Test Reactors, Argentina, Nov. 3-8, 2002, pp. 1-4.
Etherington, Nuclear Engineering Handbook, McGraw-Hill, 1958, p. 7-91.
M.M. Bretscher, et al., Neutronic Performance of High-Density LEU Fuels in Water-Moderated and Water-Reflected Research Reactors, Jul. 1996, 6 pages.
G.L. Hofman, A Short Note on High Density Dispersion Fuel, Jun. 1996, 5 pages.
JP. Durand, et al., Abstract Only, Preliminary Developments of MTR Plates With UMo Fuel, Oct. 1997, pp. 1-2.
JP. Durand, et al., LEU Fuel Development at Cerca Status as of Oct. 1998, 10 pages.
Uranium Production, Federation of American Scientists, Last updated Jun. 24, 2000, pp. 1-14.
Definition of “deplete”, p. 309 of Merriam Webster's Collegiate Dictionary tenth edition, copyright 2001.
Laucht et al., A New Standard for Uranium Metal Intended for Research Reactor Fuel Fabrication, Oct. 1998, 6 pages.
McLain et al., Reactor Handbook, Second Edition, Volume IV Engineering, Copyright 1964 by John Wiley and sons, Inc.
Kauffman et al., Nuclear Reactor Fuel Elements, 1962 Interscience Publishers, pp. 70-71; 232-233.
Bakker, et al., Using Molybdenum Depleted in 95-Mo in UMo Fuel:, Nov. 2002, 2002 International Meeting on Reduced Enrichment for Research and Test Reactors, Nov. 3-8, 2002.
Bakker Klaas
Mol Charles Adelbert
Palabrica Rick
Pillsbury Winthrop Shaw & Pittman LLP
Urenco Nederland B.V.
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