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Nuclear fuel rods

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• Nuclear fuel elements

• Nuclear fuel rods -- Data processing

• Fuel rods, Nuclear
• Reactor fuel rods
• Rods, Nuclear fuel

• Textures in Rolled Uranium Rod (declassified edition; Oak Ridge, TN: U.S. Atomic Energy Commission, Technical Information Service, 1956), by W. P. Chernock and L. W. Kates (page images at HathiTrust)
• Department of Energy's hanford spent nuclear fuel project : hearing before the Subcommittee on Oversight and Investigations of the Committee on Commerce, House of Representatives, One Hundred Fifth Congress, second session, May 12, 1998. (Washington : U.S. G.P.O. : For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office, 1998), by United States. Congress. House. Committee on Commerce. Subcommittee on Oversight and Investigations (page images at HathiTrust)
• Fabrication of fuel rods by tandem rolling / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Office of Technical Information ; [Washington, D.C.] : [Available from the Office of Technical Services, Dept. of Commerce], [1961]), by J. W. Lingafelter, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Evaluation of failed hot gas isostatic pressed fuel rods / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by C. J. Baroch, C. B. Boyer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Multi-rod burnout at high pressure / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by E. E. Polomik, E. P. Quinn, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Engineering development of fluid-bed fluoride volatility processes. (Argonne, Ill. : Argonne National Laboratory, 1964), by G. J. Vogel, W. J. Mecham, E. L. Carls, and Argonne National Laboratory. Chemical Engineering Division. ANL. (page images at HathiTrust)
• On the steady-state thermal stresses in cylindrical fuel pins due to axial variations in their internal heat-generation rate / (Argonne, Ill. : Argonne National Laboratory, 1966), by Richard A. Valentin, U.S. Atomic Energy Comission. ANL., and Argonne National Laboratory. Reactor Engineering Division. ANL. (page images at HathiTrust)
• Reactivity changes of a fast reactor core due to elastic-plastic strain and creep / (Washington, D.C. : National Aeronautics and Space Administration ; Springfield, Va. : For sale by the Clearinghouse for Federal Scientific and Technical Information, [1969]), by Richard L. Puthoff, United States National Aeronautics and Space Administration, and Lewis Research Center (page images at HathiTrust)
• Transportation of spent rods to the proposed Yucca Mountain storage [i.e. storage facility] : hearing before the Subcommittees on Highways and Transit and Railroads of the Committee on Transportation and Infrastructure, House of Representatives, One Hundred Seventh Congress, second session, April 25, 2002. (Washington : U.S. G.P.O. : For sale by the Supt. of Docs., U.S. G.P.O. [Congressional Sales Office], 2002), by United States. Congress. House. Committee on Transportation and Infrastructure. Subcommittee on Highways and Transit and United States. Congress. House. Committee on Transportation and Infrastructure. Subcommittee on Railroads (page images at HathiTrust)
• PBF severe fuel damage test 1-3 test results report / (Washington, DC : Division of Systems Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission : For sale by the Supt. of Docs., U.S. G.P.O., 1989), by Zoel R. Martinson, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research, EG & G Idaho, and Idaho National Engineering Laboratory (page images at HathiTrust)
• Data report for the instrumented fuel assembly IFA-513 / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by E. R. Bradley, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• PWR FLECHT SEASET 21-rod bundle flow blockage task data and analysis report / (Palo Alto, Ca. : Electric Power Research Institute, [1982-]), by Electric Power Research Institute, Westinghouse Nuclear Energy Systems, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Quarterly progress report on Blowdown Heat Transfer Separate-Effects Program for October-December 1978 / ([Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research ; Springfield, Va. : National Technical Information Service, 1979), by J. D. White, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, and Oak Ridge National Laboratory. Engineering Technology Division (page images at HathiTrust)
• Assessment of FRAPCON-1 BE/EM calculated fission gas release in RISO fuel rods / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by R. Chambers, E. T. Laats, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• Properties of reactor fuel rod materials at high temperatures : final summary report : severe core damage property tests program / (Washington, DC : The Commission, 1987), by J. T. Prater, E. L. Courtright, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor Accident Analysis (page images at HathiTrust)
• BWR refill-reflood program task 4.3-single heated bundle experimental task plan / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by D. D. Jones, J. A. Findlay, L. L. Myers, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Data report for the NRC/PNL Halden Assembly IFA-432 : April 1978-May 1980 / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by E. R. Bradley, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Nuclear fuel rod behavior during normal and abnormal operating conditions-results of test PR-1 / (Idaho Falls, Idaho : EG & G Idaho, Inc., 1981), by Richard W. Garner, Richard H. Smith, Daniel T. Sparks, U.S. Nuclear Regulatory Commission, and Inc EG & G (page images at HathiTrust; US access only)
• FRAP-T4 best estimate sensitivty study / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by B. L. Hansen, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Division of Systems Safety (page images at HathiTrust)
• Gravity dominated two-phase flow in vertical rod-bundles / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by B. Singh, P. Griffith, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Massachusetts Institute of Technology (page images at HathiTrust)
• LWR fuel rod post-subcooled blowdown scoping analysis / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by R. L. Grubb, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration, and EG & G Idaho (page images at HathiTrust)
• Application of linear propagation of errors to fuel rod temperature and stored energy calculations / (Washington, D.C. : The Division : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by M. E. Cunningham, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Mechanistic considerations used in the development of the PROFIT PCI failure model / (Washington, D.C. : The Commission, 1980), by P. J. Pankaskie, U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration, and Pacific Northwest Laboratory (page images at HathiTrust)
• A study of film boiling, quench, and rewet phenomena during high pressure power-cooling-mismatch testing / (Washington, D.C. : The Commission, 1980), by Fred S. Gunnerson, Paul S. Dunphy, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, U.S. Nuclear Regulatory Commission, and EG & G Idaho (page images at HathiTrust)
• Experimental support and development of single-rod fuel codes program : summary report / (Washington, D.C. : Division of Reactor System Safety, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by D. D. Lanning, U.S. Nuclear Regulatory Commission. Division of Reactor System Safety, and Pacific Northwest Laboratory (page images at HathiTrust)
• Droplet distributions in open pipes and simulated rod bundles / (Washington, D.C. : The Commission, 1981), by R. V. Smith, R. D. Lindsted, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Wichita State University. Department of Mechanical Engineering (page images at HathiTrust)
• An assessment of hydrogen generation for the PBF severe fuel damage scoping and 1-1 test / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987), by August W. Cronenberg, Daniel J. Osetek, Richard W. Miller, Idaho National Engineering Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and EG & G Idaho (page images at HathiTrust)
• FRAP-T5 uncertainty study of five reactor transient and accident events / (Washington, D.C. : The Division : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by E. T. Laats, B. L. Hansen, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• Estimators for the binomial failure rate common cause model / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1980), by Corwin L. Atwood, EG & G Idaho, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff (page images at HathiTrust)
• Beginning-of-life date report for the instrumented fuel assembly (IFA)-527 / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, 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, 1981), by D. D. Lanning, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Reactivity initiated accident test series test RIA 1-2 fuel behavior report / (Washington, D.C. : 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, 1981), by Beverly A. Cook, Idaho National Engineering Laboratory, United States. Department of Energy. Idaho Operations Office, U.S. Nuclear Regulatory Commission, and EG & G Idaho (page images at HathiTrust)
• Quarterly progress report on fission product behavior in LWRs for the period ..., by Oak Ridge National Laboratory. Chemical Technology Division. issuing body and Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards (page images at HathiTrust)
• Multirod burst test program progress report for ... /, by Oak Ridge National Laboratory. Engineering Technology Division. issuing body and sponsor U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Quarterly technical report : SPERT project, January, February, March 1968 /, by J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission, ed. by T. G. Taxelius (page images at HathiTrust)
• Postirradiation examination results for the irradiation effects test IE-1 /, by Arthur S. Mehner, R. Scott Semken, U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation, EG & G Idaho, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, October, November, December, 1967 /, by J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission, ed. by T. G. Taxelius (page images at HathiTrust)
• Reactivity accident test results and analyses for the SPERT III e-core -- a small, oxide-fueled, pressurized-water reactor /, by R. K. McCardell, J. E. Houghtaling, D. I. Herborn, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, April, May, June1968 /, by J. C. Haire, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission, ed. by T. G. Taxelius (page images at HathiTrust)
• Fuel rod deformation in the SPERT III oxide e-core /, by W. H. Etz, Phillips Petrolium Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Quarterly technical report : SPERT project, July, August, September 1968 /, by S. O. Johnson, S. G. Forbes, Phillips Petroleum Company, and U.S. Atomic Energy Commission, ed. by T. G. Taxelius (page images at HathiTrust)
• A Monte Carlo calculation of thermal utilization /, by A. Rotenberg, Robert D. Richtmyer, A. Lapidus, New York University. Institute of Mathematical Sciences, and U.S. Atomic Energy Commission. New York Operations Office (page images at HathiTrust)
• Feasibility report for casting and extruding uranium-thorium fuel rods for Atomics International /, by W. L. Larson, sponsor North American Aviation. Atomics International Division, Inc Nuclear Metals, and issuing body U.S. Atomic Energy Commission (page images at HathiTrust)
• Inspection of the rods in JEEP during the period December 1 - 7, 1952 /, by J. Brun, sponsor Joint Establishment for Nuclear Energy Research (Netherlands and Norway), and issuing body U.S. Atomic Energy Commission (page images at HathiTrust)
• SNAP 8 development reactor nuclear analysis /, by L. D. Swenson, U.S. Atomic Energy Commission, and Rockwell International. Atomics International Division (page images at HathiTrust)
• Nondestructive testing of EBR-1 Mark III fuel elements and components / (Lemont, Ill. : Argonne National Laboratory, 1959), by W. J. McGonnagle, R. G. Myers, C. J. Renken, W. N. Beck, U.S. Atomic Energy Commission. 5893, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Fuel defect test : Borax-IV / (Lemont, Ill. : Argonne National Laboratory, 1959), by R. F. S. Robertson, V. C. Hall, U.S. Atomic Energy Commission. ANL., Ltd. Atomic Energy of Canada, and Argonne National Laboratory. Reactor Engineering Division. ANL (page images at HathiTrust)
• Layer formation by interdiffusion between some reactor construction metals / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, 1949), by J. Howard Kittel, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. ANL. (page images at HathiTrust)
• Effect of rolling temperature on the preferred orientation in rolled uranium rods / (Lemont, Ill.: Argonne National Laboratory, 1957), by M. H. Mueller, H. W. Knott, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. ANL. (page images at HathiTrust)
• Analytic solution of the steady-state wave equation in three dimensions and in irregularly shaped domains with an application to a reactor with partially inserted control rods / (Lemont, Ill. : Argonne National Laboratory, 1959), by E. J. Betinis, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. ANL. (page images at HathiTrust)
• Examination of an irradiated prototype fuel element for the Elk River reactor / (Argonne, Ill. : Argonne National Laboratory, 1961), by L. A. Neĭmark, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Examination of uranium from the first core of the EBR-I / (Argonne, Ill. : Argonne National Laboratory, 1961), by W. F. Murphy, S. H. Paine, A. C. Klank, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• The manufacture of supplemental depleted fuel rods for FCF startup / (Argonne, Ill. : Argonne National Laboratory, 1963), by N. J. Jr Carson, A. B. Shuck, H. F. Jelinek, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Ultrasonic grain size testing of Hanford fuel elements / (Richland, Wash. : U.S. Atomic Energy Commission, 1960), by C. L. Frederick, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Engineering Operation (page images at HathiTrust)
• A chart of neutron blackness for soild cylindrical rods / (Richland, Wash. : Hanford Atomic Products Operation, 1954), by G. W. Stuart, U.S. Atomic Energy Commission, and Hanford Atomic Products Operation (page images at HathiTrust)
• Quantitative determination of rolling and recrystallization textures in 600©�C- and 300©�C-rolled uranium rods / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955), by Warren P. Chernock, Paul A. Beck, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod theory for a cylindrical reactor / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service, 1955), by H. L. Garabedian, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A measurement of neutron temperature in a uranium rod-water moderated lattice / (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Intracell flux traverses and thermal utilizations, 1.027% enrichment uranium rods in light water / (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Reactor physics of Teapot. (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Extension ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1955]), by Paul R. Kasten, U.S. Atomic Energy Commission, and Oak Ridge National Laboratory (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement and analysis of uniform lattices of slightly enriched UO₂ moderated by D₂O-H₂O mixtures / (Washington, DC., : Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• An analysis of transients in a pressurized-water reactor during continuous rod withdrawal / (Columbus, OH : Battelle Memorial Institute, [1956]), by Robert F. Redmond, Joel W. Chastain, Joseph J. Stone, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Measurements of bucklings and void effects in D₂O-moderated, organic- or H₂O-cooled lattices of UO₂ rod clusters / (Aiken, South Carolina : E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1964), by Frederick D. Benton, A. E. Dunklee, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• Status report on control rod materials research and development program : technical report / (Pleasanton, Calif. : Vallecitos Atomic Laboratory, 1960), by C. G. Andre, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Status report on control rod materials research and development program : technical report / (Pleasanton, Calif. : Vallecitos Atomic Laboratory, 1960), by W. C. Ballowe, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Intercomparison measurements / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Office of Technical Information ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1961]), by William C. Ballowe, John L. Russell, Walter R. Morgan, U.S. Atomic Energy Commission, and General Electric Company (page images at HathiTrust)
• Powder fuel processing by two-pass swaging : the effect of particle size and distribution / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by C. M. Ryer, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fabrication of fuel elements by swaging / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Division of Technical Information, 1962), by E. A. Lees, General Electric Company, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• An analysis of methods in control rod theory and comparisons with experiment / (San Jose, Calif. : Vallecitos Atomic Laboratory, 1962), by G. H. Kear, M. H. Ruderman, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• An experimental parametric study of the effects of control rods on the prompt neutron decay constant in multiplying media / ([Oak Ridge, Tenn. : USAEC Division of Technical Information Extension, 1962]), by P. Meyer, W. C. Ballowe, U.S. Atomic Energy Commission, General Electric Company, and Vallecitos Atomic Laboratory (page images at HathiTrust)
• Vibration of fuel rods in parallel flow / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by E. P. Quinn, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Design and fabrication of fuel rods containing low temperature sintered pellets / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by C. J. Baroch, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Off-center control rod program (digital computer program K) / (CIncinnati, Ohio: General Electric, 1959), by C. L. Moore, General Electric Company. Aircraft Nuclear Propulsion Department. Atomic Products Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod calibrations for the SRE with thorium-uranium fuel / (Canoga Park, California : Atomics International, [1962]), by R. W. Keaten, R. A. Lewis, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fuel rod bowing in the SRE / (Canoga Park, California : Atomics International, [1962]), by H. F. Donohue, R. W. Keaten, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Detecting and eliminating fuel rod bowing in the SRE /, by R. W. Woodruff, R. W. Keaten, C. W. Griffin, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of the SRE Mark II safety rod / (Canoga Park, California : Atomics International, [1959]), by E. C. Phillips, R. G. Hoff, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Statistical treatment of hot channel factors for compact reactors /, by P. D. Cohn, H. A. Evans, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Nondestructive determination of Up235s content of SNAP fuel rods : vol. III - equipment description and production quality control applications /, by A. R. Mooers, R. C Barry, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Reactivity worths of several fast reactor control materials / ([Canoga Park, California] : Atomics International, [1965]), by R. W. Campbell, S. G. Carpenter, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of the SRE Mark I safety rod / (Canoga Park, California : Atomics International, 1959), by E. C. Phillips, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Development of the SRE thimble-type control rods : Mark I and II / (Canoga Park, California : Atomics International, 1959), by A. E. Miller, U.S. Atomic Energy Commission. Technical Information Center, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Isostatic pressing of UO₂ in high temperature metals /, by I. Sheinhartz, J. Fugardi, Sylvania-Corning Nuclear Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Release of fission gases from U0₂ /, by Benjamin Lustman, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• A theoretical method for determining the worth of control rods /, by A. F. Henry, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of the PWR Core 1 failed element detection and location system /, by C. S. Abrams, F.R. Vaughan, O.D. Parr, P.W. Frank, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fission product separation study : quarterly progress report December 1, 1956 - February 28, 1957, Job 2077. (West Orange, New York : Vitro Laborartories, 1957), by Union Carbide Nuclear Company, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• In-pile measurement of the thermal conductivity of irradiated metallic fuel /, by T. H. Bauer, J. W. Holland, issuing body University of Chicago, and issuing body Argonne National Laboratory (page images at HathiTrust)
• GAPCON-THERMAL-3 verification and comparison to in-reactor data /, by D. D. Lanning, C. L. Mohr, F. E. Panisko, U.S. Nuclear Regulatory Commission. Fuel Behavior Research Branch, United States. Department of Energy, and Pacific Northwest Laboratory (page images at HathiTrust)
• Fuel rod behavior during test PCM-2 /, by Arthur S Mehner, Krishna Vinjamuri, EG & G Idaho, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Crossflow mixing between parallel flow channels during boiling :, by D. S. Rowe, C. W. Angle, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• Entrainment and deposition studies in two-phase cross flow : comparison between air-water and steam-water in a square horizontal duct / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by R. J. Berryman, C. D. Wade, J. C. Ralph, England) Atomic Energy Research Establishment (Harwell, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• PBF severe fuel damage scoping test : test results report / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986), by Alan D. Knipe, Daniel J. Osetek, Scott A. Ploger, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and EG & G Idaho (page images at HathiTrust)
• Pulsed eddy current instrument for measuring sodium levels of EBR-II fuel rods / (Lemont, III. : Argonne National Laboratory, 1961), by Kunio Ono, W. J. McGonnagle, Argonne National Laboratory. ANL., and U.S. Atomic Energy Commission. ANL. (page images at HathiTrust)
• Irradiations of U-20Pu-10Fs alloy fuel rods / (Lemont, III. : Argonne National Laboratory, 1965), by W. N. Beck, R. J. Fousek, J. H. Kittel, Argonne National Laboratory. ANL., and U.S. Atomic Energy Commission. ANL. (page images at HathiTrust)
• Hazards summary report on the transient reactor test facility (TREAT) / (Lemont, Ill. : Argonne National Laboratory, 1958), by D. R. MacFarlane, James F. Boland, G. A. Freund, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. ANL. (page images at HathiTrust)
• Preferred orientation in rolled and in recrystallized high-purity uranium rod / (Lemont, Ill. : Argonne National Laboratory, 1959), by M. H. Mueller, H. W. Knott, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Irradiation of extrusion-clad uranium-2 w/o zirconium alloy for EBR-1, Mark III / (Lemont, Ill. : Argonne National Laboratory, 1959), by J. H. Kittel, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• The calculation of radial temperature distributions in cylindrical fuel specimens during neutron irradiation / (Lemont, Ill. : Argonne National Laboratory, 1958), by Frank R. Taraba, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• The radial distribution of thermal neutron flux in cylindrical fuel specimens during neutron irradiation / (Lemont, Ill. : Argonne National Laboratory, 1959), by Frank R. Taraba, S. Hugh Paine, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Irradiation of prototype CP-4 (EBR-I) reactor fuel slugs in the CP-3' goat hole / (Lemont, Ill. : Argonne National Laboratory, 1958), by S. H. Paine, W. F. Murphy, P. J. Persiani, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Examination of irradiated experimental NRU fuel rods / (Lemont, Ill. : Argonne National Laboratory, 1959), by S. H. Paine, W. F. Murphy, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Examination of uranium-2 w/o zirconium experimental fuel slugs irradiated in EBR-I / (Argonne, Ill. : Argonne National Laboratory, 1962), by W. F. Murphy, S. H. Paine, A. C. Klank, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Examination of irradiated RaLa source fuel rod (prototype no. 2) for Los Alamos Scientific Laboratory / (Argonne, Ill. : Argonne National Laboratory, 1963), by S. H. Paine, F. L. Brown, W. F. Murphy, U.S. Atomic Energy Comission. ANL, and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• High-temperature sensors for BORAX-V boilng fuel rods / (Argonne, Ill. : Argonne National Laboratory, 1962), by E. J. Brooks, R. D. McGowan, W. C. Kramer, U.S. Atomic Energy Comission. ANL, Argonne National Laboratory. Metallurgy Division. ANL, and Argonne National Laboratory. Idaho Division. ANL (page images at HathiTrust)
• A new technique for experimental investigation of high-temperature thermal diffusivity of uranium dioxide under transient conditions / (Argonne, Ill. : Argonne National Laboratory, 1965), by Leslie D. Montgomery, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Reactor Physics Division. ANL (page images at HathiTrust)
• Summary report on irradiation of prototype EBR-II fuel elements / (Argonne, Ill. : Argonne National Laboratory, 1960), by J. H. Monaweck, E. S. Sowa, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Reactor Engineering Division. ANL (page images at HathiTrust)
• Tests of defected toria-urania fuel specimiens in EBWR / (Argonne, Ill. : Argonne National Laboratory, 1960), by R. F. S. Robertson, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Reactor Engineering Division. ANL (page images at HathiTrust)
• The manufacture of the graphite-urania fuel matrix for TREAT / (Lemont, Ill. : Argonne National Laboratory, 1960), by J. H. Handwerk, R. C. Lied, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Metallurgy Division. ANL (page images at HathiTrust)
• Physics analysis of proposals for EBWR core 2 / (Argonne, Ill. : Argonne National Laboratory, 1961), by R. Avery, C. N. Kelber, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Reactor Engineering Division. ANL (page images at HathiTrust)
• EBWR core 1A physics analyses / (Argonne, Ill. : Argonne National Laboratory, 1961), by C. Kelber, H. Iskenderian, C. Carson, K. Almenas, R. Avery, U.S. Atomic Energy Commission. ANL., and Argonne National Laboratory. Reactor Engineering Division. ANL (page images at HathiTrust)
• A retrospective analysis of aspects of the ALPR (SL-1) design / (Lemont, III. : Argonne National Laboratory, 1962), by W. J. Kann, D. H. Shaftman, Argonne National Laboratory. ANL., and U.S. Atomic Energy Commission. ANL. (page images at HathiTrust)
• Erosion resistance of swaged UO₂ following an in-reactor fuel rod cladding failure / (Richland, Wash. : Hanford Atomic Products Operation, 1961), by M. K. Millhollen, J. L. Bates, G. R. Horn, U.S. Atomic Energy Commission. AEC research and develpment report, U.S. Atomic Energy Commission. TID., U.S. Atomic Energy Commission, Hanford Atomic Products Operation, and Pacific Northwest Laboratory (page images at HathiTrust)
• Boiling burnout experiments with 19-rod bundles in axial flow / (Richland, Wash. : U.S. Atomic Energy Commission, 1963), by J. M. Batch, D. E. Fitzsimmons, G. M. Hesson, E. D. Waters, United States. National Bureau of Standards. UC., United States. Department of Energy. Office of Fusion Energy. UC., United States. National Bureau of Standards. Fracture and Deformation Division. UC., U.S. Atomic Energy Commission. AEC research and development report, United States. Energy Research and Development Administration. TID., U.S. Atomic Energy Commission. TID., Hanford Works, and Hanford Atomic Products Operation. Reactor and Fuels Laboratory (page images at HathiTrust)
• Fuel rod experience during the Spert I destructive test series with a stainless steel clad, rod-type core / ([Idaho Falls, Idaho] : Idaho Operations Office, U.S. Atomic Energy Commission, 1965), by J. Dugone, D. D. Wieland, Phillips Petroleum Company. Atomic Energy Division, U.S. Atomic Energy Commission. Idaho Operations Office, and Idaho National Reactor Testing Station (page images at HathiTrust)
• MTR shim rod calibrations / ([Idaho Falls, Idaho] : U.S. Atomic Energy Commission, Idaho Operations Office, 1961), by A. W. Brown, Phillips Petroleum Company. Atomic Energy Division, and Idaho National Reactor Testing Station (page images at HathiTrust)
• Effect of varying reduction on the preferred orientation in rolled uranium rods / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Extension ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1955]), by M. H. Mueller, P. A. Beck, H. W. Knott, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Intracell flux traverses and thermal utilizations for 1.15% enriched uranium rods in ordinary water / (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Herbert J. C. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• A survey of the reflector savings of uranium-water lattices / (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by J. Chernick, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Intracell flux traverses / (Oak Ridge Tenn. : United States Atomic Energy Commission, Technical Information Service, [1955]), by Herbert J. Kouts, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Single rod fast effects and related measurements / (Upton, N.Y. : Brookhaven National Laboratory, 1960), by Glenn A. Price, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Experimental studies of slightly enriched uranium, water moderated lattices. (Upton, NY. : Brookhaven National Laboratory, 1957), by Herbert J. C. Kouts, Rudolph Sher, U.S. Atomic Energy Commission, and Brookhaven National Laboratory (page images at HathiTrust)
• Specifications for Army Package Power Reactor (APPR-1) fuel and control rod components / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, [1957]), by R. J. Beaver, C. F. Leitten, R. C. Waugh, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Effect of varying reduction on the preferred orientation in rolled uranium rods / (Lemont, Ill. : Argonne National Laboratory, 1954), by M. H. Mueller, P. A. Beck, H. W. Knott, Argonne National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Mechanical properties of rolled uranium rods / (Lemont, Ill. : Argonne National Laboratory, 1956), by R. M. Mayfield, U.S. Atomic Energy Commission, and Argonne National Laboratory (page images at HathiTrust)
• FABC0ST 9 : a computer code for estimating fabrication costs for rod-bundle fuel elements / (Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1968), by A. L. Lotts, F. J. Homan, T. N. Washburn, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Thorium rod blanket study for thermal breeder reactor / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service Extension ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1957]), by H. C. McCurdy, Oak Ridge National Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Liquid metal fuel reactor experiment : liquid metal control rod corrosion tests / ([Washington, DC., Office of Technical Services, 1959]), by W. R. Foley, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Spectral shift control reactor basic physics program: critical experiments on lattices moderated by D₂O-H₂O mixtures / (Washington, DC., : Office of Technical Services., 1961), by T. C. Engelder, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Spectral shift control reactor basic physics program : exponential experiments at elevated temperatures on lattices moderated by D₂O-H₂O mixtures / (Washington, DC., : Office of Technical Services., 1962), by L. G. Barrett, T. C. Engelder, H. J. Worsham, U.S. Atomic Energy Commission, and Babcock & Wilcox Company (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement and analysis of perturbed lattices of slightly enriched UO₂ moderated by D₂O-H₂O mixtures / (Washington, DC., : Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Spectral shift control reactor basic physics program : measurement of k [infinity] and other lattice parameters by the small lattice experiment technique / (Washington, DC., : Office of Technical Services., 1963), by T. C. Engelder, Babcock & Wilcox Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of methods for sealing ends of PWR fuel rods / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Technical Information Service Extension, [1957]), by J. J. Vagi, D. C. Martin, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Heat transfer from parallel rods in axial flow / (Columbus, OH : Battelle Memorial Institute, [1955]), by Sherwood L. Fawcett, Joel W. Chastain, Wayne B. Dell, David A. Dingee, U.S. Atomic Energy Commission, and Battelle Memorial Institute (page images at HathiTrust)
• Fabrication of UO₂ fuel rods by vibrational compaction and pressure bonding / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 1963), by Stanley W. Porembka, Joseph J. Hauth, Charles B. Boyer, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Use of agglomerated UO₂ in pressure-bonded stainless steel-clad fuel rods / (Columbus, OH : Battelle Memorial Institute ; Washington, D.C. : Available from Office of Technical Services, U.S. Dept. of Commerce, 1963), by Robert J. Diersing, Charles B. Boyer, Stanldey W. Porembka, Edwin S. Hodge, Battelle Memorial Institute, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Forced-flow boiling in rod bundles at high pressure / (Aiken, South Carolina : E.I. du Pont de Nemours & Company, Savannah River Laboratory, 1963), by Bruce Matzner, John S. Neill, U.S. Atomic Energy Commission, Savannah River Laboratory, E.I. du Pont de Nemours & Company, and Columbia University. Heat Transfer Research Facility (page images at HathiTrust)
• Control rod calibrations in the standard pile / ([Aiken, S.C.] : E.I. du Pont de Nemours & Co., Explosives Dept., Atomic Energy Division, Technical Division, Savannah River Laboratory, [1959]), by Harold R. Fike, U.S. Atomic Energy Commission, Savannah River Laboratory, and E.I. du Pont de Nemours & Company (page images at HathiTrust)
• The fabrication of the fuel elements for the UO² high burn-up program / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Technical Information Service ; Washington, D.C. : available from the Office of Technical Services, Dept. of Commerce, 1959), by E. A. Lees, R. N. Duncan, M. E. Snyder, General Electric Company, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Relative effectiveness of reactor control materials / (San Jose, Calif. : Vallecitos Atomic Laboratory, 1959), by Richard A. Becker, John L. Russell, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Relative effectiveness of reactor control materials : Technical report (Supplement) / (San Jose, Calif. : Vallecitos Atomic Laboratory, 1961), by Walter R. Morgan, William C. Ballowe, John L. Russell, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Preparation of self bonded borides / ([Oak Ridge, Tenn.] : United States Atomic Energy Commission, Division of Technical Information ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1960]), by Earl W. Hoyt, Vallecitos Atomic Laboratory, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• A method for the comparative evaluation of reactor control materials / (San Jose, Calif. : General Electric Company, 1960), by T. J. Pashos, J. L. Russell, G. D. Ritland, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Economic comparison of control rod materials / (San Diego, Calif. : General Electric Company, Atomic Power Equipment Dept., 1961), by T. J. Pashos, H. E. WIlliamson, G. D. Ritland, U.S. Atomic Energy Commission, and General Electric Company. Atomic Power Equipment Department (page images at HathiTrust)
• A survey of new cadmium materials for possible reactor application / (Oak Ridge, Tenn. : United States Atomic Energy Commission, Office of Technical Information ; [Washington, D.C. : Available from the Office of Technical Services, Dept. of Commerce, 1960]), by S. Siegel, General Electric Company, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Determination of lifetime of the B₄C-in-tubes control rod / (San Jose, Calif. : General Electric Company, Atomic Power Equipment Dept., 1961), by Frederic Henry Megerth, U.S. Atomic Energy Commission. Division of Technical Information, and General Electric Company (page images at HathiTrust)
• Investigation of B₄C-NI electro dispersions for control rod applications / (San Jose, Calif. : General Electric Company, Atomic Power Equipment Dept., 1961), by H. E. WIlliamson, K. C. Anonty, D. L. Zimmerman, U.S. Atomic Energy Commission. Division of Technical Information, and General Electric Company (page images at HathiTrust)
• Burnout conditions for single rod in annular geometry, water at 600 to 1400 PSIA / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by E. Janssen, J. A. Kervinen, General Electric Company. Atomic Power Equipment Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Examination of 304 stainless steel cladding from cold-swaged and rolled fuel rods / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1962), by W. V. Cummings, R. E. Blood, D. R. Lewis, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• UO₂ swaged powder fuel rod failures at high thermal performance conditions / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1963), by T. J. Pashos, B. Weidenbaum, R. C. Nelson, M. F. Lyons, General Electric Company. Atomic Power Equipment Department, U.S. Atomic Energy Commission, and Joint U.S.-Euratom Research and Development Program (page images at HathiTrust)
• Design and fabrication of fuel rods clad with stainless-steel-lined zircaloy-2 / (Oak Ridge, Tenn. : U.S. Atomic Energy Commission, Division of Technical Information, 1964), by C. J. Baroch, Vallecitos Atomic Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• High-temperature hydraulic rod control / (Cincinnati, Ohio : General Electric, Aircraft Nuclear Propulsion Dept., 1960), by General Electric Company. Light Military Electronics Department, U.S. Atomic Energy Commission, and General Electric Company. #b Aircraft Nuclear Propulsion Department (page images at HathiTrust)
• Control rod theories evaluation based upon measurements of control rod worths in SM-I-2 reactor assemblies / (Cincinnati, Ohio : General Electric, Aircraft Nuclear Propulsion Dept., 1960), by J. W. Zwick, General Electric Company. Aircraft Nuclear Propulsion Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Exponential experiments with water-metal rod lattices : preliminary report on problem assignment 303-X25P / (Oak Ridge, Tennessee : United States Atomic Energy Commission, Technical Information Service ;, 1955), by T Arnette and U.S. Atomic Energy Commission (page images at HathiTrust)
• Development of shim-safety control rod for the Hallam Nuclear Power Facility / (Canoga Park, California : Atomics International, [1963]), by L. B. Copeland, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Irradiation test of gadolinium and samarium oxides for the HNPF control rod program /, by T. E. Redding, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Hydraulic characteristics of HNPF 8-rod fuel element /, by R. J. Begley, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Calibration of the SRE shim rods by the oscillation method / (Canoga Park, California : Atomics International, [1960]), by C. W. Griffin, J. G. Lundholm, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Magnetic pulse swaging of APM-UOb2s fuel rods /, by E. C. Supan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Nondestructive determination of uranium-235 content of SNAP fuel rods : volume II statistical methods for evaluating data obtained from counting experiments /, by M. A. Greenfield, R. L Koontz, C. T Nelson, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Flux hardening in fuel rods / (Canoga Park, California : Atomics International, [1960]), by E. U. Vaughan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Irradiation of UO₂ fuel rods : the X-1-L experiment /, by John D. Eichenberg, F. P. Mrazik, Richard M. Lieberman, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Development and properties of silver-base alloys as control rod materials for pressurized water reactors /, by I. Cohen, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Measurement of the thermal conductivity of metal-clad uranium oxide rods during irradiation /, by I. Cohen, John D. Eichenberg, B. Lustman, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The zircaloy-2 in-pile tube for the NRX Central Thimble /, by Richard M. Lieberman, U.S. Atomic Energy Commission, Westinghouse Electric Corporation, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• A lattice of slightly enriched UO₂ fuel rods partly immersed in light water /, by D. R. Harris, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Fission gas release in PWR Core 1 blanket fuel rods upon conclusion of seed 1 life /, by B. Rubin, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Isotopic analyses of irradiated natural uranium dioxide fuel rods from PWR Core 1 : preliminary results /, by C. D. Sphar, P. S. Lacy, J. H. Leonard, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• The properties of hafnium from a PWR Core 1 control rod after one seed life exposure /, by G. J. Salvaggio, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Fabrication defects observed in PWR core 1 blanket fuel rods /, by L. R. Lynam, J.G. Goodwin, G.J. Salvaggio, E.F. Losco, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Examination of PWR Core 1 blanket fuel rods for microstructure changes, hydrogen pickup, burst strength, and fission gas release at the end of the second seed life /, by L. R. Lynam, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Properties of a hafnium control rod after exposure during two seed lives in pwr core 1 /, by G. J. Salvaggio, J.P. Bacca, F.A. Nichols, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Metallurgical examination of fuel rod from PWR-1 blanket at the end of the second seed life /, by L. R. Lynam, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Metallurgical examination of PWR Core 1 blanket fuel rods at the end of the third seed life /, by L. R. Lynam, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Properties of a hafnium control rod after exposure during three seed lives in PWR Core 1 /, by G. J. Salvaggio, K.J. Longua, S. Kass, J.G. Weinberg, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Saxton plutonium program quarterly progress report for the period ending ... (Pittsburgh, Pa. : Westinghouse Electric Corporation, Atomic Power Division.), by U.S. Atomic Energy Commission. New York Operations Office and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• Yankee Core Evaluation Program, quarterly progress report for the period ending ... (Pittsburgh, Pa. : Westinghouse Electric Corporation, Atomic Power Division.), by U.S. Atomic Energy Commission. New York Operations Office and Westinghouse Electric Corporation. Atomic Power Division (page images at HathiTrust)
• Results of critical experiments in loose lattices of UO₂ rods in H₂O /, by V. E. Grob, J. D. Cleary, F. L. Kelly, R. D. Leamer, D. F. Hanlen, P. W. Davison, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Power density and burnup distributions in Yankee Core I /, by J. D. McGaugh, R. H. Chastain, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Developments in the casting department of the metal production plant at Iowa State College /, by Harley A. Wilhelm, U.S. Atomic Energy Commission. Technical Information Service Extension, and Iowa State College (page images at HathiTrust)
• Absorption of neutrons by black control rods / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, [1955]), by H. Hurwitz, G. M. Roe, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Interaction of black control rods / (Schenectady, N.Y. : Knolls Atomic Power Laboratory, General Electric Company, [1956]), by J. C. Stewart, J. H. Smith, U.S. Atomic Energy Commission, General Electric Company, and Knolls Atomic Power Laboratory (page images at HathiTrust)
• Study of fuel temperature and flow effects of plugging in SRE fuel /, by R.C. Noyes, U.S. Atomic Energy Commission, and North American Aviation. Atomics International Division (page images at HathiTrust)
• RODCOST : a program for calculating the cost of fabricating UOb2 sand PuOb2s-UOb2 fuel rods as a function of design /, by G. L. Simmons, J. B. Burnham, B. M. Cole, Battelle Memorial Institute. Pacific Northwest Division. issuing body, U.S. Atomic Energy Commission, and Pacific Northwest Laboratory (page images at HathiTrust)
• Saxton Plutonium Program semiannual progress report for the period ending December 31, 1966 /, by R. S. Miller, U.S. Atomic Energy Commission. New York Operations Office, Westinghouse Electric Corporation. Nuclear Fuel Division, and Euratom (page images at HathiTrust)
• Plant instrumentation program : quarterly progress report for the period ending June 30, 1970 /, by J. C. Limpert, U.S. Atomic Energy Commission. Brookhaven Office, and Westinghouse Nuclear Energy Systems (page images at HathiTrust)
• Behavior of defective PWR fuel rods during power ramp and film boiling operation /, by Douglas W Croucher, Idaho National Engineering Laboratory, EG & G Idaho, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• MATPRO - Version 11 (Revision 1) : a handbook of materials properties for use in the analysis of light water reactor fuel and behavior /, by Gregory A. Reymann, Donald L. Hagrman, U.S. Nuclear Regulatory Commission, Idaho National Engineering Laboratory, and United States. Department of Energy. Idaho Operations Office, ed. by Richard E. Mason (page images at HathiTrust)
• Quarterly progress report on fission product behavior in LWRs for the Period October--December 1978 /, by A. P Malinauskas, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research, Oak Ridge National Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• An evaluation of the in-pile pressure data from instrumented fuel assemblies IFA-431 and IFA-432 /, by E. R Bradley, R. E. Williford, D. D. Lanning, M. E. Cunningham, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Startup data report for NRC/PNL Halden Assembly IFA-513., by Donald D Lanning, Mitchel E Cunningham, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Gap conductance test series fuel characterization data report /, by Malati K. Charyula, Deborah K. Kerwin, EG & G Idaho, U.S. Nuclear Regulatory Commission, and Idaho National Engineering Laboratory (page images at HathiTrust)
• Description and characterization of evaluation models in FRAPCON-1 /, by E. T. Laats, R. Chambers, United States. National Technical Information Service, United States Government Printing Office, and U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration (page images at HathiTrust)
• Final data report for the instrumented fuel assembly (IFA)-432 /, by E. R Bradley, D. D. Lanning, M. E. Cunningham, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Reactor safety research programs : quarterly report, January-March 1981 /, by S. K Edler, Pacific Northwest Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• PBF LOCA test LOC-6 fuel behavior report /, by James M Broughton, Philip E. MacDonald, Daniel W. Golden, Donald L. Hagrman, Krishna Vinjamuri, Idaho National Engineering Laboratory, EG & G Idaho, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Reactor safety research programs : quarterly reports /, by S. K Edler, Pacific Northwest Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Evaluation of power reactor fuel rod analysis capabilities : phase 1 topical report /, by Dennis R Coleman, D. L. Harrison, Control Data Corporation. Utility Associates International, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• End-of-irradiation data report for the instrumented fuel assembly (IFA)-527 /, by M. E Cunningham, D. D. Lanning, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Evaluation of power reactor fuel rod analysis capabilities : phase 2, topical report /, by Dennis R Coleman, Control Data Corporation. Utility Associates International, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Dry spent fuel storage test plan for final nondestructive fuel rod examination /, by Charles S Olsen, EG & G Idaho, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Experiment data report for multirod burst test (MRBT) bundle B-4 /, by A. W Longest, J. L. Crowley, R. H. Chapman, Oak Ridge National Laboratory. Engineering Technology Division, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research (page images at HathiTrust)
• Irradiation performance of Piqua Core I fuel elements /, by J. L. Arnold, North Amercian Aviation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Prototypic thermal-hydraulic experiment in NRU to simulate loss-of-coolant accident / (Washington, D.C. : The Commission : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : National Technical Information Service, 1981), by C. L. Mohr, U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, and Pacific Northwest Laboratory (page images at HathiTrust)
• Development and evaluation of B₄C-graphite control-rod materials for the HTGR / (San Diego, California : General Atomic Division of General Dynamics Corporation ; Washington, D.C. : Technical Services, Department of Commerce ;, 1962), by W. V. Goeddel, U.S. Atomic Energy Commission, and General Dynamics Corporation. General Atomic Division (page images at HathiTrust; US access only)
• FRAP-T6 : a computer code for the transient analysis of oxide fuel rods / (Washington, D.C. : The Commission : The Office : Available from GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission ; Springfield, Va. : Available from National Technical Information Service, 1983), by L. J. Siefken, EG & G Idaho, United States. Department of Energy. Idaho Operations Office, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• Precharacterization report for instrumented fuel assembly (IFA)-527 / (Washington, D.C. : Division of Accident Evaluation, Office of Nuclear Regulatory Research, 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, 1981), by M. E. Cunningham, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation, and Pacific Northwest Laboratory (page images at HathiTrust)
• An assessment of LWR fuel-failure propagation potential : literature survey / (Washington, D.C. : Division of Systems Safety, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission : GPO Sales Program, Division of Technical Information and Document Control, U.S. Nuclear Regulatory Commission : Springfield, Va. : National Technical Information Service, 1980), by August W. Cronenberg, J. H. Scott, U.S. Nuclear Regulatory Commission. Division of Systems Safety, and Los Alamos Scientific Laboratory (page images at HathiTrust)
• FRAPCON-2 developmental assessment / (Washington, D.C. : The Commission, 1981), by Gary A. Berna, W. N. Rausch, D. D. Lanning, Pacific Northwest Laboratory, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Melting and forming of SER fuel rods / (Canoga Park, California : Atomics International, [1960]), by P. S. Drennan, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Criticality experiments with subcritical clusters of 2.35 Wt% and 4.31 Wt% 235U enriched UO₂ rods in water with steel reflecting walls /, by S. R Bierman, E. D. Clayton, United States. National Technical Information Service, United States Government Printing Office, Fuel Cycle U.S. Nuclear Regulatory Commission. Division of Safeguards, and Pacific Northwest Laboratory (page images at HathiTrust)
• Stored energy calculation : the state of the art /, by M. E Cunningham, C. R. Hann, R. E. Williford, A. R. Olsen, D. D. Lanning, Pacific Northwest Laboratory, U.S. Nuclear Regulatory Commission. Fuel Behavior Research Branch, and United States. Department of Energy (page images at HathiTrust)
• ANS54, a computer subroutine for predicting fission gas release /, by W. N. Rausch, F. E. Panisko, Pacific Northwest Laboratory, U.S. Nuclear Regulatory Commission. Division of Systems Safety. Core Performance Branch, United States Government Printing Office, and United States. National Technical Information Service (page images at HathiTrust)
• Reactor safety research programs, quarterly report / ([Washington, D.C.?] : Division of Reactor Safety Research), by U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Technology, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• MTR rods as fission product sources for industrial sterilization : engineering feasibility study and cost estimate. Job 24 (New York, New York : Vitro Corporation of America ;, 1954), by General Dynamics Corporation. General Atomic Division, Kellex Corporation, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Fission product separation study : quarterly progress report September 27-November 30, 1956, Job 2077 (West Orange, New York : Vitro Laborartories ;, 1956), by General Dynamics Corporation. General Atomic Division, Kellex Corporation, Vitro Corporation, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Resonance escape probability of a lattice of multi-rod fuel elements / (Canoga Park, California : Atomics International, [1959]), by C. H. Skeen, W. W. Brown, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Measurement of the SRE power coefficients and reactor parameters utilizing the oscillation techniques / (Canoga Park, California : Atomics International, [1960]), by C. W. Griffin, J. G. Lundholm, North American Aviation. Atomics International Division, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Buckling of graphite moderated lattices containing seven rod fuel clusters / (Canoga Park, California : Atomics International, 1956), by F. L. Fillmore, U.S. Atomic Energy Commission. Technical Information Center, and North American Aviation. Atomics International Division (page images at HathiTrust)
• Measurements of thermal utilization, resonance escape probability, and fast fission factor of water moderated slightly enriched uranium lattices /, by A. Z. Kranz, Bettis Atomic Power Laboratory, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Kinetic and buckling measurements on lattices of slightly enriched uranium or UO₂ rods in light water /, by J. R. Brown, B. H. Noordhoff, J. C. Andrews, J. J. Volpe, F. S. Frantz, D. R. Harris, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Dimensional inspection of irradiated PWR Core 1 blanket fuel /, by L. D. Larson, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Examination of PWR Core 1 blanket fuel rods for microstructure, hydrogen pickup, and burst strength /, by B. Rubin, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Evaluation of isotopic content of irradiated natural uranium dioxide fuel rods PWR Core 1 /, by C. D. Sphar, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Over-all evaluation of blanket fuel removed from PWR Core 1 during the first refueling of the seed /, by F. Schwoerer, Westinghouse Electric Corporation, U.S. Atomic Energy Commission, and Bettis Atomic Power Laboratory (page images at HathiTrust)
• Physics calculations for control rods in the first Yankee core /, by William H. Arnold, Yankee Atomic Electric Company, Westinghouse Electric Corporation. Atomic Power Division, and U.S. Atomic Energy Commission. Technical Information Service Extension (page images at HathiTrust)
• Microscopic lattice parameters in single-and multi-region cores : a comparison of theory and experiment /, by P. W. Davison, G. H. Minton, H. A. Risti, B. Jennings, J. D. Cleary, Westinghouse Electric Corporation. Atomic Power Department, and U.S. Atomic Energy Commission (page images at HathiTrust)
• Control rod evaluation by means of perturbation theory /, by F. L. Fillmore, U.S. Atomic Energy Commission, and North American Aviation. Atomics International Division (page images at HathiTrust)
• The thermal and mechanical behavior of a xenon-filled fuel rod as a function of burnup /, by Mitchel E Cunningham, Rick E Williford, Donald D Lanning, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• PBF-LOCA test series : test LOC-11 : test results report /, by J. R. Larson, Richard K. McCardell, Leo K. Sepold, Jay W. Spore, James M. Broughton, EG & G Idaho, Idaho National Engineering Laboratory, and U.S. Nuclear Regulatory Commission (page images at HathiTrust)
• LOCA simulation in the national research universal reactor program : data report for the third materials experiment (MT-3) / (Washington, D.C. : U.S. Nuclear Regulatory Commission, 1983), by C. L Mohr, Charles L. Wilson, G. E. Russcher, R. K. Marshall, G. M. Hesson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Experiment operations plan for the MT-3 experiment in the NRU reactor /, by G. E Russcher, M. D. Freshley, L. J. Parchen, Charles L. Wilson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Technology (page images at HathiTrust)
• BWR refill-reflood program task 4.3-single heated bundle experimental task plan : addendum 1, stage 3 - separate Effects bundle /, by D. D. Jones, United States. National Technical Information Service, United States Government Printing Office, General Electric Company. Nuclear Engineering Division, Electric Power Research Institute, and U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research (page images at HathiTrust)
• Irradiation history and interim postirradiation data for IFA-432 /, by D. D. Lanning, E. R. Bradley, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Experiment operations plan for the TH-2 experiment in the NRU reactor /, by G. E Russcher, M. D. Freshley, L. J. Parchen, C. L. Wilson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• LOCA simulation in the national research universal reactor program : postirradiation examination results for the third materials experiment (MT-3) /, by W. N. Rausch, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Experiment operations plan for the TH-3 experiment in the NRU Reactor /, by G. E Russcher, M. D. Freshley, L. J. Parchen, Charles L. Wilson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)
• Experiment operations plan for the MT-4 experiment in the NRU reactor /, by G. E Russcher, M. D. Freshley, B. J. Webb, G. M. Hesson, R. K. Marshall, L. J. Parchen, Charles L. Wilson, Pacific Northwest Laboratory, and U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation (page images at HathiTrust)

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