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Reactor Development Program Progress Report: April 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: March 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Radiolysis of Organic Fluids, Annual Progress Report: October 1, 1961-September 30, 1962

Description: From introduction: This report reviews the Susie program (particularly reactor dosimetry and data analysis) as well as other items that represent a smaller share of the total effort.
Date: January 15, 1963
Creator: Bolt, R. O.; Burrous, M. L.; Carroll, J. G.; Hall, K. L.; Sweeney, M. A. & Tobriner, M. W.
Partner: UNT Libraries Government Documents Department
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Stratospheric Monitoring Program

Description: "Results of the continuing stratospheric flight test evaluation program for the Del Model I Electrostatic Precipitator Sampler and the Del Electrical Discharge Altimeter are described and discussed. Only one of four balloon launches reached floating altitude. The altimeter obtained an altitude recording consistent with concurrent aneroid barocoder readings. The reported gross gamma concentration for the precipitator sampler was approximates 25 and 80% higher than those of the two simultaneous d… more
Date: March 15, 1963
Creator: Cravitt, S.; Lilienfeld, P.; Foldes, A. & Lippmann, M.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Seventeenth Quarter, August-October 1963

Description: From introduction: "This is the seventeenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: November 15, 1963
Creator: Flock, W. L.
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Fifth Quarterly Progress Report, April 1-June 30, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The development of pulsed neutron source techniques for large power reactors has led to a new theoretical model recently developed by E. Garelis and J.L. Russell, Jr. The theory is presently based on a bare, one-group model with m-delayed precursors and takes all spatial modes into account. Results indicate, however, that the app… more
Date: July 15, 1963
Creator: Garelis, Edward & Meyer, P.
Partner: UNT Libraries Government Documents Department
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Development of Pulsed Neutron Application to Power Reactor Start-Up Procedures. Sixth Quarterly Progress Report, July 1-September 30, 1963

Description: Activities in a program to develop techniques in the use of pulsed neutron sources to measure shutdown parameters related to large thermal power reactors are reported. The development of pulsed neutron source techniques for large power reactors has led to a new theoretical model recently developed by E. Garelis and J.L. Russell, Jr. The theory is presently based on a bare, one-group model with m-delayed precursors and takes all spatial modes into account. Results indicate, however, that the app… more
Date: October 15, 1963
Creator: Garelis, Edward & Meyer, P.
Partner: UNT Libraries Government Documents Department
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Grain Growth of UO2. Part I

Description: Abstract: (1) Grain growth in UO2 pellets was studies between 100 C and 2600 C. The pellets were encapsulated in small vacuum-tight tungsten containers in an argon atmosphere. (2) The grain size-time relationship could be expressed by an equation. A low exponent, m>_ 1/3, was found in those experiments and is related to the type of UO2 investigated. An activation energy of 65 kcal/mole was obtained for the grain growth process. The time exponent, m, increased with increasing temperature if the … more
Date: August 15, 1963
Creator: Hausner, H.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
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Environmental Testing of a B4C-Ni Prototype Control Rod

Description: Summary: A prototype control rod containing absorber plates made from an electro- deposited dispersion of boron carbide in nickel was tested in the VBWR. It was exposed to the reactor environment of 545 degree F boiling water and thermal neutron fluxes (perturbed) which ranged from 0.6 to 1.1 x 10/sup 13/ nv for 2236 hours over a period of six months. The maximum B/sup 10/ burnup achieved during the test period was 1.8 percent. After irradiation, the rod was examined. The results of the examina… more
Date: October 15, 1963
Creator: Megerth, F. H. & Zimmerman, D. L.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

Description: From introduction: "This is the fourteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: January 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Thirteenth Quarter, July-September 1962

Description: From introduction: "This is the thirteenth in a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: May 15, 1963
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: April 1 - June 30, 1963

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 831 MWD/T during the quarter which brings the tot… more
Date: July 15, 1963
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 30, 1963

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) has been modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of … more
Date: October 15, 1963
Creator: Robkin, M. A.
Partner: UNT Libraries Government Documents Department
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Residual and Fission Gas Release from Uranium Dioxide

Description: Abstract: Residual and fission gas release from UO2 were studied in the laboratory and in in-reactor experiments. Arc-fused powder and sintered pellets were used to determine the rate of evolution and types of residual gases as a function of temperature. Fission gas release was related to the average UO2 temperature and fission gas release calculations were made using the latest thermal conductivity values, isotopic half lives, and branching ratios available in the literature. The results obtai… more
Date: July 15, 1963
Creator: Spalaris, C. N. & Megerth, F. H.
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; First Quarterly Progress Report, February - March 1963

Description: Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date: April 15, 1963
Creator: Tippets, F. E.
Partner: UNT Libraries Government Documents Department
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A Uranium Dioxide Fuel Rod Center Melting Test in the Vallecitos Boiling Water Reactor

Description: Technical report describing that as part of the AEC Fuel Cycle Program, tests are being conducted to evaluate the significance of current fuel design limitations that do not permit the maximum fuel temperature to exceed the melting point of UO2. The reliability of prediction of the fuel rod operating conditions that will cause melting of the UO2 was evaluated by means of a calibration test conducted in the Vallecitos Boiling Water Reactor. Conclusions: (a) The central portion of the 3.15-cm dia… more
Date: November 15, 1963
Creator: Williamson, H. E. & Hoffmann, J. P.
Partner: UNT Libraries Government Documents Department
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