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Ionization Chambers for Environmental Radiation Measurements

Description: From Introduction: "In this report, a detailed description will be given of each of the ionization chambers used, including in each case a discussion of the methods of calibration and of techniques utilized in inferring dose readings."
Date: February 1963
Creator: Shambon, Arthur; Lowder, Wayne M. & Condon, William J.
Partner: UNT Libraries Government Documents Department
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Experimental Radiation Measurements in Conventional Structures: Part 2. Comparison of Measurements in Above-Ground and Below-Ground Structures From Simulated and Actual Fallout Radiation

Description: Report concerning the protection offered against radioactive fallout offered by two types of structures at the Nevada Test Site. Differences between above ground and underground structures are measured and compared to data taken from actual fallout conditions.
Date: February 1963
Creator: Burson, Z. G. (Zolin G.)
Partner: UNT Libraries Government Documents Department
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Operating Characteristics of the Lauterbach and Dautrebande Aerosol Generators

Description: From Abstract: "The air flow through the jet, the effect of a pre-humidifier on the water vapor content of the jet air, the cooling effect of the jet air on the generator solution, and the amount of water vapor carried away by the jet air were also determined and the results are discussed."
Date: February 1963
Creator: Mercer, T. T.; Tillery, M. I. & Flores, M. A.
Partner: UNT Libraries Government Documents Department
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Study of Requirements and Suitability of Available Reactors for Fast Fuel Tests

Description: Report issued by the APDA over studies conducted on the requirements of reactors for fuel testing. As stated in the summary, "the purpose of this study is to determine the requirements for radiation space for fast reactor fuel testing and to determine the capability of existing Commission and private test and power reactors to meet these requirements" (p. 7). This report includes tables, and illustrations.
Date: February 23, 1963
Creator: Doyle, T. A.; Duffy, J. G.; Jens, W. H.; McHugh, W. E.; Page, E. M. & Warberg, H. S.
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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Porosity gain from increase in core radius and fuel mass in Tory II-C

Description: A set of calculations has been done to determine the amount by which the volume of solid material in a Tory II-C core can be reduced with respect to the total core volume. Three separate problems were studied. In each case, some change was made which by itself would increase the K[sub eff] of the reactor. Then, in order to keep K[sub eff] unchanged, a certain amount of core material was removed. The calculations were done by means of the one-dimensional neutronic diffusion code ZOOM. The base problem ZR 1008 on which the variations were made is a cross section of Tory II-C as represented in two dimensions by ANGIE problem RZ 501. The cross section is taken at a distance of 0.3 of the length of the reactor from the front surface, and the Z dimension is adjusted in ZR 1008 so that K[sub eff] is the same as for RZ 501.
Date: February 14, 1963
Creator: Kane, W.E. & Cole, A.G.
Partner: UNT Libraries Government Documents Department
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Yankee Core Evaluation Program Quarterly Progress Report: October-December 1962

Description: Quarterly report regarding the activities of the Yankee Core Evaluation Program, the purpose of which is to evaluate the performance of the core used in the Yankee Plant and to compare actual performance with predictions, as well as the revision of designs to address any differences between actual and predicted performance.
Date: February 1963
Creator: Westinghouse Electric Corporation. Atomic Power Division.
Partner: UNT Libraries Government Documents Department
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Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Description: Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date: February 1, 1963
Creator: Holland, J. W.
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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Development of Batch Formulation Equations for Graphite Fuel Elements

Description: The development of equations used for determination .. starting weights of the individual mix batch constituents is presented. Experimental data resulting from batches compounded in this manner are shown for uranium loading, carbon density, and composite density of as graphitized natural uranium loaded fuel elements.
Date: February 26, 1963
Partner: UNT Libraries Government Documents Department
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BURNOUT CONDITIONS FOR SINGLE ROD IN ANNULAR GEOMETRY, WATER AT 600 TO 1400 PSIA

Description: Tests were run to determine burnout conditions for sn electrically heated rod in a circular tube with an annular flow path for the upward water flow. The conditions correspond to those which might exist in a reactor core. The burnout results for the basic test geometry (straight concentric annulus) showed that a plot of burnout heat flux vs quality is a straight line with a negative slope, and that the burnout heat flux is increased by a decrease in flow or an increase in pressure, while the hydraulic diameter has a maximum effect on the flux at 0.25 to 0.5 inch. A correlation of the results is given for a certain range of conditions. The following modifications of the basic test geometry were also tested: eccentric rod, simulated spacer, sandblasted rod, and rough liner. The eccentric rod and sandblasted rod decreased the burnout heat flux, while the simulated space had no effect, and the flux for the rough liner is greater than for the smooth liner. The basic test geometry data are compared with other internally heated annular data and with multirod data. (D.L.C.)
Date: February 1, 1963
Creator: Janssen, E. & Kervinen, J.A.
Partner: UNT Libraries Government Documents Department
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Comments on Proposed Lasl Ln$sub 2$ System

Description: This report addresses the comments on proposed LASL LN$sub 2$ system.
Date: February 1, 1963
Creator: Kutilek, J.L.
Partner: UNT Libraries Government Documents Department
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Deformation Twinning in Face-Centered Cubic Metals. Technical Report No. 1

Description: A review is presented of work on deformation twinning in fcc metals. Experiments which prove the existence of deformation twins are described, the characteristics of the twins are reviewed, and the stresses required for their production are analyzed. The dislocation models which have been proposed to account for the nucleation of deformation twins are reviewed. A model is proposed for the propagation of twins. (D.L.C.)
Date: February 1, 1963
Creator: Venables, J. A.
Partner: UNT Libraries Government Documents Department
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The Large Component Test Loop-Description and Operating Capabilities

Description: The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth)
Date: February 18, 1963
Creator: Atz, R. W.
Partner: UNT Libraries Government Documents Department
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Comments on E-Mad Phase II Drawings Received February 6, 1963

Description: This document reflects our comments on the drawings and design information that we have received. It is therefore contingent upon the drawings and specifications which we have not as yet received from Vitro Engineering Company.
Date: February 13, 1963
Creator: Svasek, A.J.
Partner: UNT Libraries Government Documents Department
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