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FUEL ELEMENT GRAPPLE AND FUEL ELEMENT HOLD-DOWN LATCH DEVELOPMENT--LARGE SGR FUEL HANDLING

Description: A fuel element hold-down device, which is an integral part of the fuel element assembly, was developed to lock reactor fuel to the bottom grid plate. Concurrently with the hold-down latch development, a fuel bandling machine grapple capable of setting, releasing, and checking the hold-down device was developed. (auth)
Date: December 28, 1963
Creator: Ybarra, R.M.
Partner: UNT Libraries Government Documents Department
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Internal graphite moderator forces study, C and K Reactors

Description: The purpose of this study was to determine the maximum forces that can be imposed by the graphite moderator on prospective VSR channel sleeves. In order to do this, both the origins and modes of transmission of the forces were determined. Forces in the moderator stack that are capable of acting on a block or group of blocks may originate from any of the following primary effects: Contraction of graphite due to irradiation; thermal expansion of graphite; frictional resistance to motion; resistan… more
Date: October 28, 1963
Creator: Cooley, D. E.
Partner: UNT Libraries Government Documents Department
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Reduction of Plutonium (VI) to Plutonium(III) and (IV) by Sodium Nitrite

Description: The use of anion exchange for final Pu purification in the Redox facility requires the adjustment of Pa(VI) to Pu(IV). Two methods of reduction were investigated: ferrous sulfamate and nitrite. The ferrous sulfamate method was adopted. Data on reduction of Pu(VI) to Pu(IV) and Pu(III) by nitrite are presented. The reduction by nitrite was found to be dependent on nitrite concentration, temperature, acidity, ferric ion concentration, and time, and it is possible to obtain >90% reduction to Pu… more
Date: October 28, 1963
Creator: Colvin, C. A.
Partner: UNT Libraries Government Documents Department
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Secondary Missiles Generated by Nuclear-Produced Blast Waves

Description: Report from Operation Plumbob regarding an experiment investigating secondary missiles created by blast waves from nuclear detonations of three different yeilds.
Date: October 28, 1963
Creator: Bowen, I. Gerald; Franklin, Mary E.; Fletcher, E. Royce & Albright, Ray W.
Partner: UNT Libraries Government Documents Department
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A GENERALIZED SHIELDING STUDY FOR NUCLEAR ELECTRIC SPACE POWER PLANTS

Description: The weights and thicknesses of two-layer W-- LiH shadow shields were calculated for SNAP-2, -8, and (assumed) -50 reactors. The shields are shaped as spherical sectors with haif-angles up to 30 deg and are sized so that no part of the reactor is visible within the volume subtended by the shield. Weights and thicknesses are presented for both manned and unnaanned vehicles over a wide range of reactor thermal powers, operating durations, reactorpayload separation distances, and allowable radiatio… more
Date: August 28, 1963
Creator: Berry, E. R.
Partner: UNT Libraries Government Documents Department
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Uniformly Reactive Uranium Dioxide from a Single Oxidation-Reduction Cycle

Description: Abstract: By use of a modified thermobalance and reactor as the primary experimental tool for sample preparation and evaluation, a process has been developed by which parent uranium feed materials of a widely variable reactivity and composition may be converted to a uniformly reactive uranium dioxide.
Date: August 28, 1963
Creator: Orrick, N. C.; Jones, C. G.; Hale, C. F.; Barber, E. J. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department
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Laboratory development of a process for recovering uranium from Rover fuel by combustion, liquid-phase chlorination with hexachloropropene, and aqueous extraction

Description: Declassified 24 Sep 1973. The purpose of this work was to develop a process for recovering the uranium from spent Rover fuels. Only one reactor is used, and the process involves a 4-hr combustion of the fuel in oxygen at about 800 deg C, a 4-hr chlorination of the U/sub 3/O/sub 8/-Nb/ sub 2/O/sub 5/ ash in refluxing hexachloropropene at 180 deg C, dissolution-extraction of the UCl/sub 4/ and NbCl/sub 5/ products at room temperature by dilute nitric acid, and extraction of the uranium from the r… more
Date: June 28, 1963
Creator: Gens, T.A. & Borne, T.B.
Partner: UNT Libraries Government Documents Department
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MOUND LABORATORY PROGRESS REPORT FOR JUNE 1963

Description: 3 8 ; 9 4 5 7 5 C 9 E ; < : 7over a 1456-day period. The half life was calculated to be 12.355 plus or minus 0.0l0 years, based on measurements in three calorimeters. The yields of /sup 208/Po and /sup 209/Po from the irradiation of multicurie quantities of /sup 210/Po were calculated. Production of small quantities of /sup 208/Po and /sup 209/Po is possible by the (n,xn) reaction; however, large quantities of /sup 210/Po would be present in the /sup 208/Po--/sup 209/Po sample. On the basis of … more
Date: June 28, 1963
Creator: Eichelberger, J.F.; Grove, G.R. & Jones, L.V.
Partner: UNT Libraries Government Documents Department
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Summary of BeO Development Work for the Experimental Beryllium Oxide Reactor Program

Description: The Experimental Beryllium Oxide Reactor is described. The configurations and properties of BeO blocks are discussed. Various BeO shapes were fabricated and tested. BeO specimens of selected compositions and densities were irradiated. Dimensional changes due to radiation were in the range below 1.4% as determined from micrometer measurements. Some of the specimens in the highest exposure region of the capsule exhibited radial fractures. (M.C.G.)
Date: June 28, 1963
Creator: Johnson, D. E.
Partner: UNT Libraries Government Documents Department
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Tensile and Impact Properties of Selected Materials From 20 to 300 ºK

Description: Report giving the tensile and impact properties of structural materials that were experimentally determined at temperatures from 20 to 300 ºK. Tensile properties of a few materials were also determined at 4 ºK. The properties experimentally determined were the yield strength, tensile strength, elongation, and reduction of area, the stress versus strain curve, and the impact energy. The test equipment and procedures are described. The individual data are presented in tables, and the average resu… more
Date: June 28, 1963
Creator: Warren, K. A. & Reed, R. P.
Partner: UNT Libraries Government Documents Department
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ANNEALING OF GAMMA RAY INDUCED CHANGES IN ANTIMONY DOPED GERMANIUM

Description: An investigatiori of the annealing of the radioinduced carrier concentration change in Sb-doped Ge in the range 370 to 455 l K was made. The irradiations were conducted at liquid nitrogen temperature using Co/ sup 60/ gamma irradiation. A model that explains the observed behavior is presented. On the basis of the model, the observed annealing consists of vacancy diffusion simultaneously to impurity sites and annihilation centers. Analysis of the activation energy for the annealing process yield… more
Date: May 28, 1963
Creator: Pigg, J.C.
Partner: UNT Libraries Government Documents Department
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DESCRIPTION OF PRINTED OUTPUT FROM INTRANUCLEAR CASCADE CALCULATION

Description: ABS>A detailed description of the printed output sheets from the intranuclear cascade calculation described in ORNL3383 is given. The three analysis codes --analysis codes I and II and an evaporation code --that were written to organize the raw data of the output tape are considered. (auth) A tabulation of the neutron total cross section of U/sup 233/ as a function of neutron energy from 0.07 to 10,000 ev, measured with the ORNL fast chopper time- of-flight neutron spectrometer is given. (auth)
Date: May 28, 1963
Creator: Bertini, H.W.
Partner: UNT Libraries Government Documents Department
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Effect of Massive Neutron Exposure on the Distortion of Reactor Graphite

Description: Distortion of reactor-grade graphites was studied at varying neutron exposures ranging up to 14 x 10/sup 21/ neutrons per cm/sup 2/ (nvt)/sup */ at temperatures of irradiation ranging from 425 to 800 deg C. This exposure level corresponds to approximately 100,000 megawatt days per adjacent ton of fuel (Mwd/ At) in a graphite-moderated reactor. A conventionalcoke graphite, CSF, and two needle-coke graphites, NC-7 and NC-8, were studied. At all temperatures of irradiation the contraction rate of … more
Date: May 28, 1963
Creator: Helm, J. W. & Davidson, J. M.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator (Part III)

Description: In two previous reports nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Stanford University. Results are now given for two additional cases. (auth)
Date: March 28, 1963
Creator: Alsmiller, R. G., Jr.; Alsmiller, F. S. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
open access

Calibration of Control Drums in a Sub-Critical Assembly

Description: A method of calibrating control drums in a subcritical assembly with a source is given here as an to WANL- TMI- 458 which discusses the measurement of shutdown reactivity in a subcritical core
Date: February 28, 1963
Creator: Rothman, A. B.
Partner: UNT Libraries Government Documents Department
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Control rod studies

Description: This study was undertaken to answer questions asked regarding the required rod stroke for control of modified Tory II-C reactors. All problems described were solved with the Angie code and based on Tory-II-C design problems, RZ 501 and RZ 502, representing hot and cold reactors respectively.
Date: February 28, 1963
Creator: Cole, A.
Partner: UNT Libraries Government Documents Department
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The Diffusion of Lithium in Aluminum

Description: The diffusion of lithium in aluminum was measured at various temperatures with diffusion couples of aluminum-LiAl. The activation energy, E, is 33.3 kcal/mol, and the diffusion factor, Do, is 4.5 cm{sup2}/sec. (auth)
Date: February 28, 1963
Creator: Costas, L. P.
Partner: UNT Libraries Government Documents Department
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Nucleon-Meson Cascade Calculations: Transverse Shielding for a 45-Gev Electron Accelerator. Part Ii

Description: In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)
Date: February 28, 1963
Creator: Alsmiller, R. G., Jr.; Alsmiller, F. S. & Murphy, J. E.
Partner: UNT Libraries Government Documents Department
open access

A PRELIMINARY EXAMINATION OF THE FORMATION AND UTILIZATION OF TEXTURE AND ANISOTROPY IN ZIRCALOY-2

Description: The anisotropy of mechanicai properties in Zircaloy-2 associated with preferred orientation developed during manufacture has caused many difficulties in the fabrication and utilization of mill products. A preliminary examination of the development and utilization of texture preparatory to an experimental study of anisotropy in Zircaloy-2 tubing is presented. The development of preferred orientation during manufacture of Zircaloy-2 plate, strip, and tubing is qualitatively analyzed in terms of t… more
Date: February 28, 1963
Creator: Picklesimer, M.L.
Partner: UNT Libraries Government Documents Department
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