Nuclear fuel elements

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• Nuclear engineering
• Nuclear fuels
• Nuclear reactors

• Nuclear fuel elements -- Analysis
• Nuclear fuel elements -- Computer programs
• Nuclear fuel elements -- Congresses
• Nuclear fuel elements -- Data processing
• Nuclear fuel elements -- Design and construction
• Nuclear fuel elements -- Effect of radiation on
• Nuclear fuel elements -- Experiments
• Nuclear fuel elements -- Handling
• Nuclear fuel elements -- Inspection
• Nuclear fuel elements -- Materials
• Nuclear fuel elements -- Mathematical models
• Nuclear fuel elements -- Models
• Nuclear fuel elements -- Research
• Nuclear fuel elements -- Security measures
• Nuclear fuel elements -- Storage
• Nuclear fuel elements -- Testing
• Nuclear fuel elements -- Thermal properties
• Nuclear fuel claddings
• Nuclear fuel rods

• Fuel elements
• Nuclear reactors -- Fuel elements
• Reactor fuel elements

• A Failure Analysis for the Low-Temperature Performance of Dispersion Fuel Elements (Oak Ridge, TN: Oak Ridge National Laboratory, 1960), by J. R. Weir (page images at HathiTrust)
• Fundamental aspects of nuclear reactor fuel elements : prepared for the Division of Reactor Development and Demonstration, Energy Research and Development Administration / Donald R. Olander. (Oak Ridge, Tenn. : Technical Information Center, Office of Public Affairs, Energy Research and Development Administration ; Springfield, Va. : available [from] National Technical Information Service, U.S. Dept. of Commerce, 1976), by Donald R. Olander (page images at HathiTrust)
• LMFBR fuel analysis : task C : reliability aspects of LMFBRs. (Washington : Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Project Management, 1978-), by U.S. Nuclear Regulatory Commission. Division of Project Management (page images at HathiTrust)
• Purification of reactor fuels using liquid zinc / by J.B. Knighton, L. Burris, Jr. and H.M. Feder. (Argonne, Ill. : Argonne National Laboratory, 1961), by J. B. Knighton (page images at HathiTrust)
• Physics analysis of proposals for EBWR core 2 / by R. Avery and C.N. Kelber. (Argonne, Ill. : Argonne National Laboratory, 1961), by R. Avery (page images at HathiTrust)
• EBWR core 1A physics analyses / by R. Avery ... [et al.].. (Argonne, Ill. : Argonne National Laboratory, 1961) (page images at HathiTrust)
• Flux trap experiments in D₂O-moderated thoria-urania cores / by K.E. Plumlee. (Argonne, Ill. : Argonne National Laboratory, 1964), by K. E. Plumlee (page images at HathiTrust)
• Nitridation of crucible skulls from melt refining / by T.R. Johnson, G.F. Brunzie, and R.K. Steunenberg. (Argonne, Ill. : Argonne National Laboratory, 1960), by T. R. Johnson (page images at HathiTrust)
• Sodium and bismuth liquid metal fuel systems : a literature search to June 30, 1957 / by Richard C. Vogel and Walton A. Rodger. (Lemont, Ill. : Argonne National Laboratory, 1958), by Richard C. Vogel (page images at HathiTrust)
• Fabrication of EBR-II, core I fuel pins / by H.F. Jelinek, N.J. Carson, Jr., and A.B. Shuck. (Lemont, III. : Argonne National Laboratory, 1962), by H. F. Jelinek (page images at HathiTrust)
• Fabrication of EBR-II, core I fuel elements / by N. J. Carson ... [et. al.]. (Lemont, III. : Argonne National Laboratory, 1962) (page images at HathiTrust)
• EBR-II fuel irradiation facilities / by R.J. Schiltz, J.H. Monaweck, and E.S. Sowa. (Lemont, Ill. : Argonne National Laboratory, 1958), by R. J. Schiltz (page images at HathiTrust)
• A re-evaluation of fission ratios measured in ZPR-III critical assemblies / by William G. Davey and Paul I. Amundson. (Argonne, Ill. : Argonne National Laboratory, 1964), by William G. Davey (page images at HathiTrust)
• Chlorination of uranium and fission product oxides in molten halide media / by J.P. LaPlante, D.A. Wenz, and R.K. Steunenberg. (Argonne, Ill. : Argonne National Laboratory, 1962), by J. P. LaPlante (page images at HathiTrust)
• Removal of EBWR fuel element scale by slurry honing / by Ira Charak. (Argonne, Ill. : Argonne National Laboratory, 1960), by Ira Charak (page images at HathiTrust)
• Estimation of fission product spectra in fuel elements discharged from the power breeder reactor and the experimental breeder reactor no. 2 / by I.G. Dillon and Leslie Burris, Jr. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, 1954), by I. G. Dillon (page images at HathiTrust)
• Experimental support and development of single-rod fuel codes program : summary report / prepared by D. D. Lanning, Pacific Northwest Laboratory. (Washington, D.C. : Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. D. Lanning (page images at HathiTrust)
• Fuel rod failure as a consequence of departure from nucleate boiling or dryout / Robert Van Houten. (Washington, D.C. : Division of Reactor Safety Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1979), by Robert Van Houten (page images at HathiTrust)
• LMFBR fuel analysis task C : reliability : final report, October 1977 - November 1978 / L. Cave, W.E. Kastenberg, School of Engineering and Applied Science, University of California Los Angeles. (Washington, D.C. : Division of Project Management, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1979), by L. Cave (page images at HathiTrust)
• Design and performance characteristics of EBR-II control rod drive mechanisms / by E. Hutter and G. Giorgis. (Argonne, Ill. : Argonne National Laboratory, 1964), by E. Hutter (page images at HathiTrust)
• A device to simulate the service thermal conditions in EGCR-type fuel elements / W.R. Martin and J.R. Weir. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1961), by W. R. Martin (page images at HathiTrust)
• The determination of sulfur in beryllium oxide and sintered beryllium oxide fuel elements / [by] Walter G. Boyle, Jr., Lewis J. Gregory, [and] William Sunderland. (Livermore, CA : University of California Lawrence Radiation Laboratory, 1963), by Walter G. Jr Boyle (page images at HathiTrust)
• Dissolution of BeO- and Al₂O₃-base reactor fuel elements. K.S. Warren, L.M. Ferris, A.H. Kibbey. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1962), by Kenneth S. Warren (page images at HathiTrust)
• Declading of PWR blanket fuel elements with aqueous ammonium fluoride solutions / L.M. Ferris. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1958), by L. M. Ferris (page images at HathiTrust)
• Preparation of alloy for first core loading of EBR-II / by Donald C. Hampson. (Argonne, Ill. : Argonne National Laboratory, 1961), by Donald C. Hampson (page images at HathiTrust)
• Removal of chloride ion from Darex process dissolver solution / J.E. Mendel, W.W. Schulz. (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by J. E. Mendel (page images at HathiTrust)
• Power reactor fuels reprocessing progress report on corrosion studies / R.F. Maness. (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by R. F. Maness (page images at HathiTrust)
• High temperature aqueous corrosion of aluminum-plutonium and aluminum-silicon-plutonium alloys / H.C. Bowen. (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by H. C. Bowen (page images at HathiTrust)
• Preparing Zircaloy-2 for autoclave testing : the pickling and rinsing process / D.W. Shannon and B. Griggs. (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by D. W. Shannon (page images at HathiTrust)
• Evaluation of aluminum for use in reactors cooled by high-temperature recirculating water / J.A. Ayres. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. A. Ayres (page images at HathiTrust)
• Fission product distribution in ORR fuel elements / A.L. Colomb. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1960), by A. L. Colomb (page images at HathiTrust)
• Comparison of boiling burnout data for 19-Rod bundle fuel elements spaced with "wire" and "warts" / by J.M. Batch and G.M. Hesson. (Richland, Wash. : Hanford Atomic Products Operation, 1964), by J. M. Batch (page images at HathiTrust)
• The Sulfex process : terminal development report / F.D. Fisher. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by F. D. Fisher (page images at HathiTrust)
• The system PuO₂-ZrO₂ / D.F. Carroll. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by D. F. Carroll (page images at HathiTrust)
• Irradiation effects on uranium dioxide melting / J.A. Christensen. (Richland, Wash. : Hanford Atomic Products Operation, 1962), by J. A. Christensen (page images at HathiTrust)
• Demonstration of an irradiated UO₂ fuel recycle : first recycle / J.L. Swanson ... [et al.]. (Richland, Wash. : U.S. Atomic Energy Commission, 1961) (page images at HathiTrust)
• Nuclear safety in chemcial and metallurgical processing of plutonium / E.D. Clayton. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by E. D. Clayton (page images at HathiTrust)
• A semi-empirical method of estimating material bucklings for slightly enriched uranium-water lattices / C.L. Brown. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by C. L. Brown (page images at HathiTrust)
• Measurement of negative k [subscript] ex for a graphite uranium lattice in the PCTR / E.Z. Block, D.E. Wood. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by E. Z. Block (page images at HathiTrust)
• Aqueous corrosion of aluminum-plutonium alloys / C.H. Bloomster, Y.B. Katayama. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by C. H. Bloomster (page images at HathiTrust)
• Recovery of uranium and plutonium from sulfuric acid decladding solutions / D.E. Horner, C.F. Coleman. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959), by D. E. Horner (page images at HathiTrust)
• Decladding of Consolidated Edison Power reactor fuel by Sulfex and Darex processes : cyclic dissolution experiments / L.M. Ferris. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by L. M. Ferris (page images at HathiTrust)
• Summary report : an evaluation of the substitution of zircaloy for stainless steel in N.S. Savannah fuel-element containers / T.D. Anderson ... [et al.]. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1963) (page images at HathiTrust)
• Design and analysis of the Experimental Gas-Cooled Reactor fuel assemblies / G. Samuels. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1963), by G. Samuels (page images at HathiTrust)
• Development of corrosion-resistant aluminum alloys for high-temperature water service / H.C. Bowen. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by H. C. Bowen (page images at HathiTrust)
• Mechanisms and kinetics of uranium corrosion and uranium core fuel element ruptures in water and steam / V.H. Troutner. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by V. H. Troutner (page images at HathiTrust)
• Confinement and collection of UO₂ fines from a shearing operation / G. Rey. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by G. Rey (page images at HathiTrust)
• Corrosion associated with fluorination in the Oak Ridge National Laboratory fluoride volatility process / A.P. Litman, A.E. Goldman. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1961), by A. P. Litman (page images at HathiTrust)
• Sulfex process : depassivation of stainless steel / T.A. Gens. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959), by T. A. Gens (page images at HathiTrust)
• Evaluation of the boron content in fuel plates fabricated for the first core loading of the Army SM-1 Reactor, formerly APPR-1 / J.H. Cherubini, C.F. Leitten, Jr., and R.J. Beaver. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1962), by Julian H. Cherubini (page images at HathiTrust)
• Final report : shear development for the nonproduction fuels reprocessing program / V.P. Kelley. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by V. P. Kelley (page images at HathiTrust)
• Material buckling measurements on graphite-uranium systems at Hanford : a summary tabulation / D.E. Wood. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by D. E. Wood (page images at HathiTrust)
• Corrosion associated with hydrofluorination in the Oak Ridge National Laboratory fluoride volatility process / A.E. Goldman, A.P. Litman. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1961), by A. E. Goldman (page images at HathiTrust)
• Process for dissolution of Borax IV reactor fuel : laboratory development / L.M. Ferris. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by L. M. Ferris (page images at HathiTrust)
• Design and thermal analysis of EGCR control rods / J.W. Michel. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by J. W. Michel (page images at HathiTrust)
• Analysis of stress and strain in spherical shells of pyrolytic carbon / J.W. Prados, J.L. Scott. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by J. W. Prados (page images at HathiTrust)
• The zirflex process : terminal development report / P.W. Smith. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by P. W. Smith (page images at HathiTrust)
• Effect of wire wraps on pressure drop for axial turbulent flow through rod bundels / E.D. Waters. (Richland, Wash. : U.S. Atomic Energy Commission, 1963), by E. D. Waters (page images at HathiTrust)
• Annealing of warm-extruded zircaloy-2 to an ultrafine grain size / R.L. Knecht. (Richland, Wash. : Hanford Atomic Products Operation, 1961), by R. L. Knecht (page images at HathiTrust)
• Corrosion evaluation of nickel-base alloys developed to contain power reactor fuel dissolvents / R.F. Maness. (Richland, Wash. : U.S. Atomic Energy Commission, 1961), by R. F. Maness (page images at HathiTrust)
• Surface temperatures of irradiated ORR fuel elements cooled in stagnant air / J.F. Wett, Jr. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1960), by J. F. Jr Wett (page images at HathiTrust)
• Project Aquarium : laboratory and field corrosion tests for the Geneva Conference Reactor / J.L. English, A.R. Olsen, and E.G. Bohlmann. (Oak Ridge, Tenn., Oak Ridge National Laboratory, 1959), by J. L. English (page images at HathiTrust)
• A study of problems associated with release of fission products from ceramic fuels in gas-cooled reactors / J.A. Lane ... [et al.]. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959) (page images at HathiTrust)
• Critical experiments and nuclear safety at Oak Ridge National Laboratory / A.D. Callihan. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1956), by A. D. Callihan (page images at HathiTrust)
• Boron-aluminum and boron-uranium-aluminum alloys for reactor application / W.C. Thurber, J.A. Milko, R.J. Beaver. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1957), by W. C. Thurber (page images at HathiTrust)
• Mechanical cladding-fuel interactions during thermal cycling of metal-clad fuel elements / W.R. Martin. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1965), by W. R. Martin (page images at HathiTrust)
• Quality evaluation of zircaloy-2 sheath tubing / P.L. Farnsworth, H.P. Oakes, R.B. Socky. (Richland, Wash. : U.S. Atomic Energy Commission, 1959), by P. L. Farnsworth (page images at HathiTrust)
• Reprocessing uranium-molybdenum alloy fuels : dissolution in concentrated nitric acid / W.W. Schulz. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by W. W. Schulz (page images at HathiTrust)
• Correlation of theoretical and experimental values of the ratio of fast to thermal fissions / M.T. Lee. (Richland, Wash. : U.S. Atomic Energy Commission, 1958), by M. T. Lee (page images at HathiTrust)
• The dependence of thermal stresses in cylindrical reactor fuel elements upon the method of cooling / K.R. Merckx. (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by K. R. Merckx (page images at HathiTrust)
• Thermal utilization, thermal flux, and lattice cell shape / H. Neumann. (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by H. Neumann (page images at HathiTrust)
• Shear development for the nonproduction fuel reprocessing program : interim report / V.P. Kelley. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by V. P. Kelley (page images at HathiTrust)
• The effects of carbon content on the rate of dissolution of dingot uranium in nitric acid / A.L. Bement, J.L. Swanson. (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by A. L. Bement (page images at HathiTrust)
• Decontamination / P.S. Kingsley, M.L. Short. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by P. S. Kingsley (page images at HathiTrust)
• CRUD : a fission-product diffusion code for the CDC 3600 and IBM 7094 / G.M. Litton, C.R. Hunt. (Livermore, Ca. : Lawrence Radiation Laboratory, 1964), by G. M. Litton (page images at HathiTrust)
• The ORNL gas-cooled reactor : advanced concepts / Oak Ridge National Laboratory. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by Oak Ridge National Laboratory (page images at HathiTrust)
• Hydrofluoric acid decladding of zirconium-clad power reactor fuel elements / W.E. Clark, A.H. Kibbey. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by W. E. Clark (page images at HathiTrust)
• Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid / J.R. Flanary ... [et al.]. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1959) (page images at HathiTrust)
• Operational safety of the ORNL graphite reactor using enriched-uranium fuel / P.R. Kasten, S. Jaye, M.P. Lietzke. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1960), by P. R. Kasten (page images at HathiTrust)
• Segregation in uranium-aluminum alloys and its effect on the fuel loading of aluminum-base fuel elements / W.C. Thurber, R.J. Beaver. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by W. C. Thurber (page images at HathiTrust)
• Dissolution of sintered thorium-uranium oxide fuel in nitric acid-fluoride solutions / W.D. Bond. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1958), by W. D. Bond (page images at HathiTrust)
• Carburization and chemical treatments for recovery of uranium from stainless steel fuel elements / R.E. Adams and E.S. Bomar, Jr. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by R. E. Adams (page images at HathiTrust)
• An investigation of the corrosion resistance of brazing alloys for austenitic stainless steel fuel elements for service in 565⁰ F pressurized water / R.J. Beaver, C.F. Leitten, Jr., J.L. English. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1962), by R. J. Beaver (page images at HathiTrust)
• Darex pilot plant studies / J.J. Shefcik. (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by J. J. Shefcik (page images at HathiTrust)
• Laboratory development of a process for separating barium-140 from MTR fuel / by E. L. Anderson, R. S. MacCormack, C. M. Slansky ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1959), by Edward L. Anderson (page images at HathiTrust)
• Continuous dissolver theory. E. E. Erickson. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by E. E. Erickson (page images at HathiTrust)
• Continuous dissolver theory. E. E. Erickson. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1958), by E. E. Erickson (page images at HathiTrust)
• Continuous dissolver theory. E. E. Erickson. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1959), by E. E. Erickson (page images at HathiTrust)
• Heat transfer and fluid flow studies with boundary layer turbulence promoters / N. Kattchee and W. V. Mackewicz. (San Ramon, Calif. : Aerojet-General Corporation, Aerojet-General Nucleonics, 1963), by Nicholas Kattchee (page images at HathiTrust)
• Electrolytic dissolution of nuclear fuels with alternating current / F.M. Warzel, K.F. Smith, J.B. Colson. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by F. M. Warzel (page images at HathiTrust)
• Summary report on materials for the GCRE-II / Ray Carpenter and Anthony Del Grosso. (San Ramon, Calif. : Aerojet-General Corporation, Aerojet-General Nucleonics, 1960), by Ray Carpenter (page images at HathiTrust)
• Local thermal flux distribution in SPERT III fuel elements by the spherical harmonics method / by C.W. Reich. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1957]), by C. W. Reich (page images at HathiTrust)
• An analysis of nonboiling reactivity feedback mechanisms in pressurized power excursions in the SPERT III reactor / Richard W. Garner. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by Richard W. Garner (page images at HathiTrust)
• Containment of iodine-131 released by the RaLa process / by G.K. Cederberg, D.K. MacQueen. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by G. K. Cederberg (page images at HathiTrust)
• The dissolution of iron and nickel in dilute aqua regia / R.D. Cannon. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by Richard Douglas Cannon (page images at HathiTrust)
• Nuclear aspects of proposed 19-plate fuel assemblies / G.H. Hanson, H.L. McMurry. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service Extension, 1952), by G. H. Hanson (page images at HathiTrust)
• Statistical analysis of MTR fuel element nno-destructive assay data / F.H. Tingey, F.P. Vance. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 16198), by F. H. Tingey (page images at HathiTrust)
• Design and development of a fuel plate surface thermocouple for special power excursion reactor tests / submitted by W.H. Giedt, D.L. Rall. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1957]), by Warren H. Giedt (page images at HathiTrust)
• Spherical harmonic methods in slab geometry / D.R. Metcalf and G.A. Cazier. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by Dale Robert Metcalf (page images at HathiTrust)
• An out-of-pile electron irradiation circulating loop for fouling studies / by R.A. Mengelkamp, P.S. Hudson, and J.C. Hillyer. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962), by R. A. Mengelkamp (page images at HathiTrust)
• Heat transfer in ETR fuel assemblies for cycle 13 / V.A. Walker. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1959]), by V. A. Walker (page images at HathiTrust)
• Double P-1 spherical harmonics approximation in slab geometry / by D.R. Metcalf and G.A. Cazier. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1960]), by Dale Robert Metcalf (page images at HathiTrust)
• Laboratory studies for HTRE fuel reprocessing / R.D. Cannon, B.E. Paige, K.L. Rohde ; M.W. Roberts, editor. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1961]), by R. D. Cannon (page images at HathiTrust)
• Densities of ammonium fluoride-ammonium nitrate-ammonium hexafluozirconate solutions / J.L. Teague, D.P. Pearson. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by J. L. Teague (page images at HathiTrust)
• Pilot plant studies with a six-inch diameter fluidized bed calciner / D.R. Evans ; operation and development work performed by E.S. Grimmett ... [et al.]. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by D. R. Evans (page images at HathiTrust)
• Heat transfer in the ETR / V.A. Walker. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by V. A. Walker (page images at HathiTrust)
• A non-destructive method for fuel assaying / S.G. Forbes. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1953), by S. G. Forbes (page images at HathiTrust)
• Use of "Binal" in reactor control rods / R.E. Heffner. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by R. E. Heffner (page images at HathiTrust)
• A summary of the 1962 fuel element fission break in the MTR / J. W. Dykes, J. D. Ford, and K. R. Hoopingarner. ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by J. W. Dykes (page images at HathiTrust)
• Salt-phase chlorination of reactor fuels. E.M. Vander Wall, H.T. Hahn, D.L. Bauer. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by E. M. Vander Wall (page images at HathiTrust)
• Stainless steel process wastes. M.E. McLain, D.W. Rhodes. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1960), by Milton E. McLain (page images at HathiTrust)
• Review of research and development at the Idaho Chemical Processing Plant on the electrolytic dissolution of nuclear fuel / C.M. Slansky, K.L. Rohde, H.T. Hahn. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by C. M. Slansky (page images at HathiTrust)
• Stainless steel wastes. K.T. Faler, D.R. Anderson. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by Kenneth T. Faler (page images at HathiTrust)
• Interim report on the calcination of zirconium fluoride waste solutions / R.L. Hickok, J.S. Madachy. (Idaho Falls, Idaho : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by R. L. Hickok (page images at HathiTrust)
• An improved aqueous process for zirconium alloy nuclear reactor fuels. K.L. Rohde ... [et al.]. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1962) (page images at HathiTrust)
• Metallurgical examination of a melted SPERT-I type-B fuel plate / W.O. Schaffnit. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by W. O. Schaffnit (page images at HathiTrust)
• Hydraulics of modified fuel elements for ETR / by R.G. Beck. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1958]), by R. G. Beck (page images at HathiTrust)
• Effect of recirculation of dissolver effluent on the continuous dissolution of aluminum in mercury-catalyzed nitric acid / R.H. Ray. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1964), by R. H. Ray (page images at HathiTrust)
• Effect on flux of a fuel plate in reflector / J.W. Webster, H.L. McMurry. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1953), by J. W. Webster (page images at HathiTrust)
• Neutron flux distributions in the Materials Testing Reactor. G.O. Bright. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1953), by G. O. Bright (page images at HathiTrust)
• Plutonium fuel requirements for operation of the MTR / H.L. McMurry and B.W. Johnson. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1957]), by H. L. McMurry (page images at HathiTrust)
• In-pile mechanical failure of MTR fuel assemblies / L.J. Harrison. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1963), by L. J. Harrison (page images at HathiTrust)
• Spent fuel element acitivity and core burnup distribution from the MTR plutonium core loading / by J.M. Waage. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1959]), by J. M. Waage (page images at HathiTrust)
• Operating parameters and neutron flux profiles for MTR plutonium core / L.J. Harrison. ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, [1959]), by L. J. Harrison (page images at HathiTrust)
• An apparatus for the determination of total gas in fuel element samples / R.I. Miller. (Richland, Wash. : U.S. Atomic Energy Commission, 1957), by R. I. Miller (page images at HathiTrust)
• Outgassing behavior of EGCR moderator graphite / J.P. Blakely, L.G. Overholser. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1964), by J. P. Blakely (page images at HathiTrust)
• Summary of nuclear physics experiments / Robert E. Quilici. (San Ramon, Calif. : Aerojet-General Corporation, Aerojet-General Nucleoncis, 1965), by Robert E. Quilici (page images at HathiTrust)
• Reactor-weight study of beryllium oxide, beryllium, lithium-7 hydride, and water as moderators with tungsten 184 structural material and uranium dioxide fuel / Robert E. Hyland. (Washington, D.C. : National Aeronautics and Space Administration : [For sale by the Office of Technical Services, Dept. of Commerce], [1962]), by Robert E. Hyland (page images at HathiTrust)
• The preliminary design of the liquid metal fuel reactor experiment / Brookhaven National Laboratory, Nuclear Engineering Department and Mechanical Engineering Division. (Upton, N.Y. : Brookhaven National Laboratory ; Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service Extension, 1956) (page images at HathiTrust)
• Reprocessing of power reactor fuels : the Enrico Fermi fast breeder reactor fuel progress report no. 2 / C.W. Pierce ... [et al.]. (Upton, N.Y. : Brookhaven National Laboratory, 1959) (page images at HathiTrust)
• Reprocessing of power reactor fuels : the Enrico Fermi fast breeder reactor fuel progress report no. 1 / C.W. Pierce, B. Manowitz. (Upton, N.Y. : Brookhaven National Laboratory, 1958), by C. W. Pierce (page images at HathiTrust)
• Uranium-water lattice compilation. Glenn A. Price. (Upton, N.Y. : Brookhaven National Laboratory, 1966), by Glenn A. Price (page images at HathiTrust)
• An evaluation of materials of construction for the Sulflex [sic] and Zirflex processes / Herbert M. Katz and Robert Isler. (Upton, N.Y. : Brookhaven National Laboratory, 1962), by Herbert M. Katz (page images at HathiTrust)
• Temperature of and stresses in cylindrical fuel elements during pile flashes : application to Brookhaven reactor / Melville Clark, Jr. (Upton, N.Y. : Brookhaven National Laboratory, 1950), by Melville Clark (page images at HathiTrust)
• Fluidized bed reprocessing of stainless steel clad UO₂ power reactor fuels / C.B. Bartlett ... [et al.]. (Upton, N.Y. : Brookhaven National Laboratory, 1965) (page images at HathiTrust)
• Reprocessing of nuclear fuels by volatility separations in fluidized beds / S.J. Wachtel ... [et al.]. (Upton, N.Y. : Brookhaven National Laboratory, 1966) (page images at HathiTrust)
• Heat transfer analysis of internally-externally cooled cylindrical fuel elements for nuclear reactors / by F. E. Tippets. (Richland, Wash. : Hanford Atomic Products Operation, 1954), by F. E. Tippets (page images at HathiTrust)
• Neutron flux distributions in the materials testing reactor. by G.O. Bright. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955), by G. O. Bright (page images at HathiTrust)
• Improvements in MTR fuel assemblies and operating procedures / by C.F. Leyse. (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1955]), by C. F. Leyse (page images at HathiTrust)
• Results of UNIVAC survey of the thermal utilization of BNL experimental lattices / by J. Chernick. (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by J. Chernick (page images at HathiTrust)
• Critical assemblies of light water moderated, slightly enriched uranium rod lattices at Brookhaven : hazards report / by Herbert Kouts. (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service Extension, [1956]), by Herbert Kouts (page images at HathiTrust)
• Critical assemblies of light water moderated, slightly enriched uranium rod lattices at Brookhaven : supplement to hazards summary report / by Herbert Kouts. (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service Extension, [1956]), by Herbert Kouts (page images at HathiTrust)
• Investigations in the system urania-neodymia / by D. Kolar, J.H. Handwerk, and R.J. Beals. (Argonne, Ill. : Argonne National Laboratory, 1962), by D. Kolar (page images at HathiTrust)
• A rechargeable pressurized fuel element irradiation facility / by D.C. Kaulitz and T.W. Evans. (Richland, Wash. : Hanford Atomic Products Operation, 1957), by D. C. Kaulitz (page images at HathiTrust)
• Investigation of the factors affecting sensitization of army package power reactor (APPR-1) fuel elements / R.J. Beaver, ... [et. al.]. (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1957) (page images at HathiTrust)

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