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Yankee Core Evaluation Program Quarterly Progress Report: July-September 1963

Description: From introduction: The potential of this study as a basis for the evaluation of reactor core design methods is very great. It represents the first opportunity of its kind in relation to the design of low enriched, uranium fueled, light water moderated reactors. Sufficient information should be available to obtain a good fit between the experimental results and a combination of basic physical data and computer programs. The degree of accuracy of this fit will be evaluated. This information will … more
Date: October 1963
Creator: Chajson, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A System for Measurement of Wall Thickness of Corroded Aluminum Reactor Process Tubes

Description: A sector gauge was developed for routine measurement and recording of wall thicknesses between the ribs and at the top of installed aluminum reactor power tubes. The basic criteria selected for the device were that it would measure and record wall thickness over the length of the tube with an accuracy of plus or minus 2 mils at an average rate of 3 min per tube. An eddy-current measuring system was used in the device.
Date: October 1963
Creator: Dulin, Ralph V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operational Control Rod Reactivity Worths From Observed Heat Generation Rates

Description: Introduction. The reactivity difference associated with a reactor change can be simply related to the coincident changes in the neutron loss and generation rates. Unfortunately, in many instances these rates are difficult to measure directly during high-level operation; thus relativity values are normally found by other methods such as buckling calculations or low-level rising period measurements. However, with certain applicable control rod systems, it may be feasible to use heat generation… more
Date: October 1963
Creator: Fredsall, J. R. & Bowers, C. E.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sorption Measurements in Ultrahigh Vacuum at Constant Pressure

Description: Introduction. Sorption of gases by surfaces is the primary step in many heterogeneous processes. Because sorption processes are in general pressure-dependent, and very fast at normal pressures, low pressure system are mandatory. In gas-metal interaction studies the flash filament technique with ribbons and filaments and Wagener's technique with evaporated films allow observations at the requisite low pressures. However, these method have two major drawbacks: (1) Since the pressure changes dur… more
Date: October 1963
Creator: Gibson, Richard.; Bergsnov-Hansen, B.; Endow, Noboru. & Pasternak, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)

Description: Report describing the dimensions, materials, and fabrication of vibrationally compacted, mixed oxide (UO2-PuO2) fuel elements for the Plutonium Recycle Test Reactor (MARK I-L). Appendix begins on page 38.
Date: October 1, 1963
Creator: Hanford Atomic Products Operation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1963 - September 1, 1963

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1963
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Collins, William R., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactivity Control Problems in the Plutonium-Fueled EBR-1 Reactor

Description: In contrast with previous EBR-1 reactor cores which were fueled with enriched uranium, the current Mark IV core is a 7 x 8-in. cylinder made of delta-stabilized plutonium alloyed with 1 1/4 w/o aluminum. The reactivity of the reactor is largely controlled by the movement of the entire outer blanket mounted on a hydraulic elevator with a travel of 80 inches. Partial meltdown occurred in November, 1955 during the last experiment scheduled for the core which was directed toward identifying the tim… more
Date: October 1963
Creator: Haroldsen, R. O. (Ray Ottley), 1928-; McGinnis, F. D. & Smith, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Fourteenth Quarterly Progress Report, July-September 1963

Description: Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development. The number of assemblies has been reduced to seven as a result of the failure of two pellet fuel assemblies. The average burnup of the group operating as of September 1 is 7500 MWD/T. (2) Task 1B-Fuel Fabrication Development. Assembly. Assembly 12S gave positiv… more
Date: October 1963
Creator: Holladay, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specific Zirconium Alloy Design Program Quarterly Progress Report: Sixth Quarter, July - September, 1963

Description: Summary: Fundamental studies in support of the alloy design work are complete except for the experimental determination of the diffusion of oxygen in alloy-doped non-stoichiometric ZrO2. Over 100 oxidation runs have now been made on samples of ZrO2 doped with 1 mole percent of the oxides of Al, Y, Fe, Cr, and Ni. The first round testing of 31 alloys is now essentially complete. Analysis of the steam corrosion rate and hydriding raw data taken at 300, 400, and 500 degrees C indicates that Zr-C… more
Date: October 1, 1963
Creator: Klepfer, H. H.; Jaech, John L.; Douglass, D. L. (David Leslie), 1931-; Blood, R. E. & Perrine, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Description: Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prediction of Two-Phase Critical Flow Rate

Description: Technical report of a proposal of an analytical model to predict two-phase critical flow rate. The model is based upon thermal equilibrium, a "lumped" treatment of the two-phase velocity (each phase is represented by a single mean velocity), and upon the neglect of frictional and hydrostatic pressure losses. A comparison, of the proposed predictions with available test results and previous analyses shows that: (1) The present model agrees very well with the published test data. (2) In contrast … more
Date: October 1963
Creator: Levy, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

ML-1 Power Determination

Description: The ML-1 is a nuclearly heated, electrical power producing plant being developed for the U. S. atomic Energy commission and the U. S. Army by Aeroject-General Nucleonics. The power plant is a compact, water-moderated, gas-cooled, nuclear reactor, coupled in a single closed cycle to a gas driven turbine-compressor set and alternator. The plant is designed to produce power up to 500 Kw electrical,using 3 Mw thermal supplied by the reactor. It will operate 10,000 hours without refueling and hav… more
Date: October 23, 1963
Creator: Lightle, Robert E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Training of Consumers Public Power District Personnel for the Operation of the Hallam Nuclear Power Facility

Description: Training of Consumers Public Power District (CPPD) operating personnel for the Hallam Nuclear Power Facility (HNPF) was carried out under two formalized training programs. Both programs were organized and directed by Atomics International (AI). The first program was conducted in 1960 while he HNPF was under construction. The second program was begun in September 1961, prior to the initial HNPF dry critical loading experiment, and was completed in February 1963. The conventional portion of S… more
Date: October 1963
Creator: Loomis, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Selection of Personnel for Reactor Operator Training

Description: Over the past six years, the hiring practices of the Reactor Operations Division of Argonne National Laboratory have been conducted to determine the highest level of personnel who would be willing to remain in the position of reactor operator. We have discontinued the hiring of personnel who have a bachelor's degree from an accredited institution or who are close to receiving such a degree. We now hire men from three general categories: (1) graduates from two-year technical institutes, (2) men… more
Date: October 23, 1963
Creator: Martens, Frederick H. (Frederick Hilbert), 1921-2012.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating and Safety Problems in a Research Reactor

Description: Abstract. The purpose of this paper is to present, in the light of 20 years of reactor-operation experience at ORNL, what is being done in preparation for operation of the HFIR (High Flux Isotope Reactor). This paper considers only the areas of staffing and training; development of operating and maintenance procedures; preoperational testing of water systems; and testing of remote handling tools. The preparatory work in other areas such as the hydraulic tests, neutron tests, etc., is not cover… more
Date: October 23, 1963
Creator: McCord, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Controlled-Environment Steam Corrosion Facility

Description: Abstract; Technical report describing a low-flow autoclave system developed for out-of-pile corrosion testing of materials in controlled environment steam up to 500 C. The system has been set up in triplicate to provide for the exposure of various zirconium alloys to steam at 300, 400, and 500 C. The oxygen and hydrogen of the steam were controlled at 25 ppm and 3 ppm, respectively, to simulate the gas conditions from radiolytic water decomposition found in a boiling water reactor. The autocla… more
Date: October 1963
Creator: Nelson, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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