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ART-04--A MODIFICATION OF THE ART PROGRAM FOR THE TREATMENT OF REACTOR THERMAL TRANSIENTS ON THE IBM-704

Description: Several recent modifications of the ART program for the study of the behavior of a nuclear reactor during various thermal transients are described. The program requires a 32,000-word IBM-704 computer with six tape units. The major modifications are provision for a slip flow model and for void reactivity contribution. (auth)
Date: July 1, 1960
Creator: Meyer, J.E. & Peterson, W.D.
Partner: UNT Libraries Government Documents Department
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CHEMICAL DECONTAMINATION OF THE ANL-2 HIGH-PRESSURE WATER LOOP

Description: The chemical decontamination of the ANL-2 Highpressure Water Loop at the MTR is described. A mixture of sodium hydroxide and potassium permanganate was first applied to oxidize partially and loosen the magnetite corrosion film on the loop surfaces. Next, the system was treated with a solution of Versenol 120 to remove and suspend the loosened oxide film. The third chemical treatment was a mixture of sulfamic acid, HEDTA, hydrazine, and Rodine 80. After the first two chemical treatments a brown residue remained, which was presumed to be manganese dioxide. The third solution completely removed all traces of residue from the first two treatments. After a delay of one MTR fuel cycle (three weeks) due to mechanical difficulties, the loop was operated for approximately 300 hours at 420 deg F and 380 psig with excess hydrogen to passivate the loop surfaces. Approximately 70% of the corrosion film was removed from the loop surfaces as a result of the chemical decontamination. (auth)
Date: July 1, 1960
Creator: Crothers, C.C.
Partner: UNT Libraries Government Documents Department
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COHERENT ELECTROMAGNETIC EFFECTS IN HIGH-CURRENT PARTICLE ACCELERATORS: I. INTERACTION OF A PARTICLE BEAM WITH AN EXTERNALLY DRIVEN RADIO-FREQUENCY CAVITY

Description: A calculation is made of the interaction of a beam of particles in an accelerator with the radio-frequency cavity that provides the accelerating mechanism of the machine. A Hamiltonian for synchrotron motion is employed that makes possible the simultaneous solution of Maxwell's equations and the Vlasov equation, so that a self-consistent distribution of particles in synchrotron phase space is determined. The effective voltage on the cavity due to the beam of charged particles is of the order of magnitude of the product of the total circulating current in the accelerator and the shunt impedance of the rf cavity. It has the net effect of producing a total voltage on the cavity which is both less than the applied voltage, and shifted in phase with respect to it. The increase in the stable phase angle required so the particles will remain in phase with the accelerating radio frequency is calculated. The decrease in total voltage and increase in stable phase angle result in a decrease in stable phase space available for acceleration, and convenient expressions are given for these quantities in terms of parameters of the accelerator. It is shown that the consequences of the induced voltage may be alleviated by increasing the voltage applied to the cavity.
Date: July 1, 1960
Creator: Neil, V. Kelvin & Sessler, Andrew M.
Partner: UNT Libraries Government Documents Department
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Consolidated Edision Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and power density distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor.
Date: July 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments with Oxide Fuel Pins

Description: This report describes the critical experiments with pin-type oxide fuel elements for the Consolidated Edison Thorium Reactor (CETR). This report also describes the measurements and gives a brief interpretation of the results in some cases
Date: July 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Critical Experiments With Oxide Fuel Pins

Description: Critical experiments with pin-type oxide fuel elements for the CETR are described. These experiments were conducted to provide data on the infinite medium properties of the lattice inside the canned elements in the various CETR loading zones and to obtain specific information on the fullsize CETR core. Measurements are described and results are interpreted. (J.R.D.)
Date: July 1, 1960
Creator: Batch, M. L. & Snidow, N. L.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor: Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods.
Date: July 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor-Reactor Vessel Internal Components Design

Description: The design functions and fabrication details for internal components of the CETR are presented and pertinent analytical stress studies are summarized. Functions of the internal components include proper orientation and support for the fuel elements, proper distribution of primary coolant within the reactor vessel, and the establishment of guide channels for the control rods. (J.R.D.)
Date: July 1, 1960
Creator: Ficor, J.; Collings, D. M.; Sandrock, R. J. & Kalen, D. D.
Partner: UNT Libraries Government Documents Department
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Control Blade Worth by Partial Water Height and Soluble Boron Methods

Description: The series of experiments described in this paper was performed to determine reactivity values of various patterns of fully inserted cruciform control blades. The experiments yielded the worth of fully inserted blade patterns in terms of their holddown characteristics.
Date: July 1960
Creator: MacKinney, Arland L. & Ball, Russell M.
Partner: UNT Libraries Government Documents Department
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CORROSION OF STAINLESS STEEL IN HNO$sub 3$-HF SOLUTIONS

Description: Studies were made on the safe handling of HHO/sub 3/-HF solutions in 304 L and 309SCb stainless-steel equipment under carefully controlled conditions. The corrosion behavior of both wrought and welded 304L and 309SCb was investigated in various HNO/sub 3/--HF solutions, ranging in HNO/sub 3/ concentration from 0 to 10.0 M and HF concentration from 0.01 to 1.5 M, at temperatures from 24 deg C to the boiling point. (auth)
Date: July 1, 1960
Creator: Kranzlein, P.M.
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date: July 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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Cost Study of a 100-Mw(E) Direct-Cycle Boiling Water Reactor Plant

Description: A technical and economic evaluation is presented of a direct-cycle light- water boiling reactor designed for natural circulation and internal steam-water separation. The reference lOO-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. (W.D.M.)
Date: July 1, 1960
Creator: Bullinger, C. F. & Harrer, J. M.
Partner: UNT Libraries Government Documents Department
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COULOMETRIC TITRATION OF URANIUM IN NITRIC ACID SOLUTIONS

Description: A coulometric titration method was developed for the determination of uranium in HNO/sub 3/ solutions. Uranium was reduced to the (IV) state and was titrated with electrolytically generated cerium(IV). The colorimetric end point was detected automatically by a photometric technique. Interference from nitrate was eliminated by the addition of urea to the titration medium. The coefficient of variation for the analysis of uranium was 3.2% for 1-mg samples and 0.3% for 100-mg samples. With the addition of urea as much as 4.5 milliequivalents of nitric acid in a 1- to 3-ml sample was tolerated. (auth)
Date: July 1, 1960
Creator: Fulda, M.O.
Partner: UNT Libraries Government Documents Department
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Effects of Irradiation on the EBWR Fuel Alloy Uranium-5 w/o Zirconium-1.5 w/ o Niobium. Final Report-Metallurgy Program 6.1.20

Description: Irradiations were made on small specimens of U-5 wt.% Zr-1.5 wt.% Nb alloy with a wide variety of fabrication histories and heat treatments in order to determine the optimum heat treatment for the fuel plates for the Experimental Boiling Water Reactor (EBW). In the time available, a heat treatment could not be found which simultaneously conferred dimensional stability and corrosion resistance to the alloy. The most effective heat treatment for dimensionally stabilizing swaged or round-rolled material was a 24-hr isothermal transformation from the gamma phase at 650 deg C. This heat treatment was subsequently used as a basis for the heat-treatment specifications for the EBWR fuel plates. In later studies on specimens cut from plates it was learned that the alloy could be adequately stabilized against irradiation growth and also made corrosion- resistent by first reducing the plate 12% in thickness by cold rolling followed by a 24-hr isothermal transformation from the gamma phase at 665 deg C, and finally quenching from 800 deg C. Irradiation growth rates of plate specimens were effectively reduced by the presence of metallurgically bonded Zircaloy-2 cladding. Flat-rolled material under irradiation generally increased in length and width and decreased in thickness. (auth)
Date: July 1, 1960
Creator: Kittel, J. H.
Partner: UNT Libraries Government Documents Department
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Estimating Safety Probabilities from Fallout Forecasts for Nevada Test Site

Description: Abstract: "Available data on wind persistence and wind forecasting capability have been applied in estimating the probability of a fallout pattern shifting from an uninhabited safe sector into a populated region. Safety probability is computed from win variability, forecasting accuracy, initial height and particle size of radioactivity landing at a point in the predicted fallout pattern, predicted wind speed, length of forecast period, and safe-sector angular width."
Date: July 1, 1960
Creator: Reed, Jack W.
Partner: UNT Libraries Government Documents Department
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EXAMINATION OF IRRADIATED EBWR CORE-1 FUEL ELEMENTS

Description: Two fuel elements were removed from the Experimental Boiling Water Reactor and examined in a hot cell. The elements had maximum burn-ups of 0.11 and 0.39 at.%. Both were disassembled and sampled for the evaluation of the effects of in-pile operation and radiation damage to the fuel. The fuel elements were in gcod condition with no ruptured.cladding, core-clad nonbonds, or excessive fuel-plate swelling or warpage. Thin samples cut from the fuel plates in element ET-51 warped and cracked, suggesting a relieving of locked-in stresses and indicating that after 0.39 at.% burn-up the fuel cores were hard, brittle, and highly stressed. The rate of fuel-plate volume increase owing to the burn-up of uranium was 6 to 7% DELTA V per at.% burn-up. Hydrogen was picked up by the fuel plates under reactor operating conditions with the probable forraation of isolated areas of small announts of zirconiura hydride. Annealing studies on sections of fuel plate at 500 and 550 deg C indicated bulk volume increases of 1 to 2% and 5 to 10%, respectively, after 500 hr. A 600 deg C anneal resulted in a bulk volume increase of 17% after 45 hr. (auth)
Date: July 1, 1960
Creator: Reinke, C.F. & Carlander, R.
Partner: UNT Libraries Government Documents Department
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