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Division of Reactor Development Programs Monthly Report- August 1959

Description: Sinterability studies on mixtures of UO2 and PuO2 powders have been continued. All of the censities from previous sintering experiments have been recalculated utilizing a somewhat different water immersion technique. Since densities of pellete obtained by physical dimensions are inaccurate due to chipping, and water immersion does not account for the open porosity, the pellets were coated with clear krylon before being immersed in water. This effectively sealed the open pores. Plots of density … more
Date: September 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Report- December 1958

Description: Two Zircaloy-clad capsules (GKH-14-19,20) containing two compacts each of high density PuO2-UO2 mixed crystal oxides were shipped to the MTR in December 2, 1958. The compacts contain 0.026 a/o PuO2, have densities of 91 percent of the theoretical value, and will generate the same specific power as an Al-1.8w/o Pu alloy rod of the same diameter would produce. Two capsules (GKH-14-21,22) have been prepared and contain three compacts each of low density, about 65 percent of the theoretical value, … more
Date: January 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Report - February 1959

Description: Plutonium Oxide Fuels. Mixtures of PWR grade UO2 containing 10, 20, 30, 40, 50, and 60 w/o PuO2 were sintered in hydrogen for 44 hours at 1600 C to get additional data on solubility in this system. Densities of all the pieces were low, approximately 80 percent of theoretical; however, solid solution formation was complete in every case. The low density material should not affect lattice parameter values, but it did slightly reduce the intensity of the reflections.
Date: March 15, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Report- July 1959

Description: Basic Studies. Sinterability studies on the isomorphous system UO2-PuO2 have continued. One-half inch diameter X 3/8'' long compacts containing physical mixtures of the two components have been heated in hydrogen. Sintered density as a function of time and temperature has been determined for times of one and eight hours up to 1600 C. In general, there seems to be minima on isothermal plots of density versus composition in the intermediate range 20-40 w/o PuO2. At concentrations greater than 40 … more
Date: August 17, 1959
Creator: McEwen, L.H.
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Report- March 1959

Description: Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
Item Type: Refine your search to only Report
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Division of Reactor Development Programs Monthly Reports-June 1959

Description: Basic Studies. Sinterability experiments in the system UO2-PuO2 have continued, and data are available at one hour hold times across the UO2-PuO2 composition limits. Sintered densities appear to be markedly dependent on pressed densities with densification occurring very rapidly at higher pressing pressures. The following table illustrates the effect of one hour at temperature on final density for pure plutonium dioxide pressed to both 40 and 60 percent of theoretical density.
Date: July 15, 1959
Creator: Lewis, M.
Item Type: Refine your search to only Report
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DOSE AND FLUX MEASUREMENTS ON GODIVA RADIATION EFFECTS EXPERIMENTS

Description: Flux and dose measurements of fast neutrons, thermal neutrons and gamma rays under perturbing conditions using Godiva as a source are described and discussed. The limitations of single monitoring devices are noted. It is pointed out that in order to improve the accuracy of flux and dose measurements in radiation effects studies, specific detectors must be used at the position of the experimental object. (auth)
Date: September 21, 1959
Creator: Harris, P.S.; Montoya, E.F. & Schweitzer, W.H.
Item Type: Refine your search to only Report
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A Double Pulse Eddy Current Testing System

Description: ing. Radiography was used to ore fter bending. The ultrainspect the alloys cores, ished fuel elements. as used to determine element core blanks. at ing fatigue tests were performed in the range 1300 to 1500 F, for frequencies of 6 and 60 cpm. Continuous traces of load and strain were made to determine relationships between stress, strain, and lifetime, for lifetimes vithin the range of 10/sup 3/ and 10/sup 5/ cycles. The data obtained indicate that fatigue strength, whether measured in stress, … more
Date: June 1, 1959
Creator: Renken, C.J. & Myers, R.G.
Item Type: Refine your search to only Report
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DYNAMIC BEHAVIOR OF BOILING REACTORS

Description: Eight boiling reactors, BORAX I, II, III, IV, EBWR, LITR, VBWR, and SPERT I,have been operated to date, and a considerable amount of information exists in regard to their tendencies toward self-induced power oscillations. Data are presented on the following characteristics of the oscillations: power, pressure, temperature, reactivity amplitudes, and their rate of change: thresholds, and harmonic content. Results from three techniques of measuring the reactor transfer function are presented: the… more
Date: May 1, 1959
Creator: Thie, J.A.
Item Type: Refine your search to only Report
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Dynamic Response of Reactor Plant to Load Changes. Section I. First Performance. Core I, Seed 1. Test Results DL-S-251 (T-612390)

Description: The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the… more
Date: November 6, 1959
Creator: Gentry, George
Item Type: Refine your search to only Report
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The Economics of Nuclear Power

Description: Economic aspects of nuclear power development in the U. S. are tabulated and graphed. Included are figures on presently operating reactors as well as those contemplated or scheduled. Also a brief description of the objectives of short- and long-range programs is given as well as tables listing some of the characteristics of each reactor. (J.R.D.)
Date: April 27, 1959
Creator: Lane, J.A.
Item Type: Refine your search to only Report
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Economies in Material Handling

Description: An annlysis of those problems connected with handling of the most common items in stores, warehouses, and yards is presented. Present methods are reviewed and new developments are discussed. It is concluded that chief among areas of improved techniques lies in the reduction of the number of times individual items have to be handled. (J.H.D.)
Date: November 1, 1959
Creator: Flaxbart, R.D.
Item Type: Refine your search to only Report
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Eddy Current Ultrasonic Transducer

Description: In the field of nondestructive testing the ultrasonic test method is used extensively. In this method ultrasonic energy generated by a transducer is caused to enter the test specimen. The effect on the transducer is cause to enter the test specimen. The effect on the transmission or reflection of the ultrasonic energy by differing test specimen structure is used as an indirect measure of test specimen characteristics.
Date: August 24, 1959
Creator: Libby, Hugo L.
Item Type: Refine your search to only Report
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Effect of Additions to Zircaloy on Hydrogen Pickup During Aqueous Corrosion

Description: An investigation was conducted into the possibility of alloy additions to Zircaloy-2 to diminish hydrogen absorption during aqueous corrosion. The nickel in Zircaloy-2 is believed to be the major constituent responsible for the relatively high hydrogen absorption. Additions of up to 0.5 wt.% antimony, arsenic, bismuth, or tellurium were selected on the basis of their known ability to poison the catalytic effects of nickel in hydrogenation reactions of other systems. Results of tests conducted f… more
Date: December 29, 1959
Creator: Berry, W. E.; White, E. L. & Fink, F. W.
Item Type: Refine your search to only Report
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Effect of Choice of Electrical Conductor on Power Requirements of Low Temperature Magnets

Description: Introduction. As has been shown by Post, the total power required to produce a strong, steady-state magnetic field is strongly dependent upon the temperature at which the electrical conductor of the magnet operates. The power required for operation at very low temperature can, in some cases, be much less than that required for ambient temperature operation. The power required for low temperature operation depends on many system characteristics which include the metal chosen for the electrical… more
Date: November 13, 1959
Creator: Mallon, Richard G.
Item Type: Refine your search to only Report
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The Effect of Fabrication Variables on the Structure and Properties of UO$sub 2$ Stainless Steel Dispersion Fuel Plates

Description: Based on the results of detailed fabrication studies, an evaluation of the effects of varying the type and size of UO/sub 2/ particles, the type and size of stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures, and atmospheres, roll-clading temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures was made for UO/sub 2/stainless steel dispersion fuel elements. Transverse tensile tests, creep-rupture tests… more
Date: February 18, 1959
Creator: Paprocki, S. J.; Keller, D. L. & Cunningham, G. W.
Item Type: Refine your search to only Report
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The Effect of Fabrication Variables on the Structure and Properties of UO₂-Stainless Steel Dispersion Fuel Plates

Description: From introduction: "This report deals with a part of the research and development studies which preceded the manufacture of fuel elements for the Gas Cooled Reactor Experiment (GCRE)." The studies evaluate the effects of varying the type and size of UO2 particles, stainless steel matrix powders, blending procedures, compacting pressures, sintering times, temperatures and atmospheres, roll-cladding temperatures and reduction rates, total cold reduction, and heat-treating times and temperatures h… more
Date: February 18, 1959
Creator: Paprocki, Stan J.; Keller, Donald L. & Cunningham, G. W.
Item Type: Refine your search to only Report
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THE EFFECT OF IMPURITIES ON IRON-CHROMIUM-YTTRIUM ALLOYS

Description: A study was made of the effect of carbon, manganese, oxygen, palladium, and sulfur on the structure and fabricability of iron-35 wt.% chronium-1 wt.% yttrium alloy. Using a vacuum-induction melting technique each of the additives except oxygen was introduced to 1-lb remelts of a single 15-lb master alloy. The master alloy and remelts were made under similar melting, pouring, and casting conditions. Oxygen was introduced as Fe/sub 2/0/sub 2/ by inertelectrode arc melting to avoid extraneous, unc… more
Date: April 27, 1959
Creator: Endebrock, Row W.; Chubb, Walston; Foster, Ellis L. & Dickerson, Ronald F.
Item Type: Refine your search to only Report
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Effect of Irradiation Upon Mechanical Properties of Zircaloy-2

Description: It is well known that neutron damage generally causes increases in the yield and ultimate strength and a decrease in ductility of a metal. There is a continuing program at HAPO to determine the extent of these changes in Zircaloy-2 as functions of integrated neutron exposure, irradiation temperature, and reactor atmosphere. Three investigations from this program will be described and the results summarized. The first investigation deals with both annealed and cold worked Zircaloy-2 irradiated a… more
Date: September 4, 1959
Creator: Bement, A. L. & Gray, D. L.
Item Type: Refine your search to only Report
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Effect of Moderator Height on Reactor and Vertical Flux Distribution in PRTR

Description: Primary control of the PRTR is achieved by regulating the level of the heavy water moderator which is held in the reactor vessel by a helium gas balance system. Emergency shutdown is effected by a gas-balanced moderator dump system which drain the moderator from the calandria at a rapid rate. This report presents a quantitative appraisal of the reactivity effects due to moderator level changes in controlling or scramming the reactor. In conjunction with the reactivity calculations, solutions we… more
Date: March 3, 1959
Creator: Reginmbal, J.J.
Item Type: Refine your search to only Report
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