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Analysis of the Zircaloy-2 Creep Data with Two Extrapolation Methods

Description: The experimental evaluation of low (10⁻⁸ in/in/hr) creep rates are costly and time consuming. Thus, in answer to a request from the design group, the creep data on Zircaloy-2 obtained at Battelle Memorial Institute is extrapolated into the low creep rate range. Because the methods of extrapolation have not been evaluated at very low creep rates on Zircaloy, two different methods are used to analyze the creep data. The methods of extrapolation are given so that future analyses can be carried out… more
Date: April 17, 1956
Creator: Merckx, K. R.
Partner: UNT Libraries Government Documents Department
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The Effect of Oxidation on the Compession Strength of CE-CEF Graphite

Description: Limitations on the maximum temperature of the pile moderator have been imposed to prevent or control the gasification reaction of the graphite stack with the pile gas atmosphere. An uncontrolled reaction would cause a loss of structural strength, density, and thermal conductivity and would thus result in an unnecessary shortening of the effective operating life of the HAPO piles. Numerous studies have been made to define the rates of reaction of the pile stack with various components of the pil… more
Date: April 11, 1956
Creator: Griggs, Bruce
Partner: UNT Libraries Government Documents Department
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Application and Operation of the 325 Building Well Counter

Description: Well-type scintillation counters have found use in many radiochemical laboratories. A gamma scintillation well counter has been used to measure the gamma activity of liquid samples in the 325 Building counting room for about a year. This well counter has been built and calibrated so that gamma activity measurements made with it can be easily compared with measurements made with the gamma scintillation counter (GSC). The well counter is electronically identical to the present GSC and differs onl… more
Date: March 8, 1956
Creator: Brauer, F. P.
Partner: UNT Libraries Government Documents Department
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Absorption by Soil of Strontium From 216-S Crib Waste

Description: A preliminary soil column experiment with a waste sample from the 207-S-11 well, which monitors the 216-S cribs, indicated that cesium was absorbed almost completely by the soil but that strontium breakthrough to ground water in the near future seemed likely. Accordingly, it was suggested that the 216-S wastes be discharged to a new disposal site, and that samples of the wastes which are currently being discharged to the 216-S cribs be obtained for soil absorption tests. The primary purpose of … more
Date: February 15, 1956
Creator: Rhodes, D. W.
Partner: UNT Libraries Government Documents Department
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A Simultaneous Scaler Control System

Description: The primary purpose of this writeup is to present a description of the electrical and mechanical features of the developed system for use in maintenance and operation of a simultaneous scaler control unit.
Date: August 15, 1955
Creator: Tomlinson, R. L.
Partner: UNT Libraries Government Documents Department
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Non-destructive Testing Hanford Fuel

Description: At present, emphasis is being given the application of nondestructive testing to the inspection of nuclear fuel in conjunction with complete product specifications. The objective is to quantitatively specify fuel quality parameters, and to measure the entire fuel production against these specifications nondestructively. Under this concept the acceptability of a given fuel element becomes a well-defined factor readily determined by appropriate nondestructive tests.
Date: June 22, 1960
Creator: Worlton, D.C.
Partner: UNT Libraries Government Documents Department
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Description: The absorption of the important fission products by plants is quantitatively presented as a concentration factor which is defined as the ratio of the fission product concentration found in the leaves to the fission product concentration found in the nutrient substrate. Of the fission products, the isotopes of strontium were found to be the most important by virtue of their high concentration factor, long half-life, and low maximum permissible amounts for animals. Iodine and barium follow in im… more
Date: May 17, 1955
Creator: Rediske, J. H.; Cline, J. F. & Selders, A. A.
Partner: UNT Libraries Government Documents Department
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Use of Hood Cells for Enclosing Low Level Radiation Processes

Description: A perspective drawing of typical hood cells arranged in series for an assembly line operation is presented. Advantages of this improved enclosure for low level radiation work are listed which recommend its use on new facilities in preference to more conventional designs.
Date: February 28, 1957
Creator: Moulthrop, H. A.
Partner: UNT Libraries Government Documents Department
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An Ultrasonic Method for Bond Testing Reactor Fuel Elements

Description: Ultrasonic testing has been investigated as a possible non-destructive method for checking the bond integrity of certain type fuel elements. Equipment has been developed to inspect experimental fuel elements for various research programs. Circuits have been devised to discriminate the size of defects and to map the areas which are unbonded.
Date: November 27, 1956
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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Technical Information for Application of Differential Pressure Transmitters in Pulse Column Bottom Interface Control Systems

Description: The information in this report is based on experience with a similar unit installed on experimental pule columns in the 321 Building. These installations were made to demonstrate the feasibility of the system. In one case, the installation on the 2A Prototype Column, the differential pressure cell (D/P cell) bottom interface control system was monitored by a capacitance-type instrument. The other installations were made on glass columns and were monitored visually.
Date: October 8, 1956
Creator: Smith, A. E.
Partner: UNT Libraries Government Documents Department
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Radioactivity Levels of the Columbia River Below Richland, Washington for the Period April, May, June 1956

Description: In the Columbia River downstream from Richland, Washington there is a gradual decrease in concentration of radioactive isotope. At any one location there are fluctuations due to factors such as dilution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit. Beta particle emitters in water upstream of McNary Dam decreased slightly due to increased river flow this quarter, with averages at various locations. Do… more
Date: October 17, 1956
Creator: Clukey, H. V.
Partner: UNT Libraries Government Documents Department
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Quarterly Progress Report Research and Development Activities in the Field of Radiological Science July - September, 1956

Description: During this quarter, the Hanford Atomic Products Operation reorganized with the elimination of the Radiological Sciences Department as a separate organizational entity. The new structure which was effective on September 1, 1956, is outlined in this report to indicate the new relationships.
Date: October 30, 1956
Creator: Healy, J. W.
Partner: UNT Libraries Government Documents Department
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Trip Report Consultation on Organic Reactor Coolants

Description: There is a continuing high interest in the development of organic coolant technology for application to future Hanford reactors. In addition to the HAPO organic program, two other programs are being sponsored by the Atomic Energy Commission. These include the Naval Reactor program, aimed at a reactor for ship propulsion, and the Civilian Power Reactor program. Because of the similarity of the technical efforts in the three programs, an attempt is being made to establish effective liaison among … more
Date: November 5, 1956
Creator: Atwood, J. M.; Cook, M. W. & Eddy, P. P
Partner: UNT Libraries Government Documents Department
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A Dripless Transfer Pipette for Radiochemical Operations

Description: Transfer operations of highly radioactive solutions by the normal transfer pipette leads in most instances to a spread of contamination in the shielded facility. In the dripless pipette, the solution is held in the reservoir by the use of the siphon principle.
Date: October 26, 1956
Creator: Wilson, A. S.
Partner: UNT Libraries Government Documents Department
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Pilot Plant Dissolution of Unjacketed Fuel Elements

Description: In the fall of 1952, a pilot plant batch dissolution study was carried out to obtain the data required for the design of the Purex Plant dissolvers. Particular emphasis was placed on the rate of dissolution and the efficiency of nitrogen oxide recovery from the dissolver off-gas. The results are presented in this report.
Date: October 15, 1956
Creator: Evans, T. F.
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of Cluster-Type Fuel Elements

Description: Cluster fuel elements meet many of the requirements of high temperature recirculating water reactors and have several advantages over solid fuel elements. Operation at higher specific power levels for a given temperature limit are attainable because of the larger heat transfer surface. Failure of a single rod in cluster does not restrict coolant flow as severely as failure of a solid fuel element, hence the number and severity of stuck charges can be reduced.
Date: November 19, 1956
Creator: Boyd, C. L.
Partner: UNT Libraries Government Documents Department
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Physics Research Quarterly Report: July, August, September 1955

Description: Under the general heading of Reactor Lattices are reported a new method of calculating resonance escape probabilities, results for the effective mass of a proton bound in the water molecule, and a comparison of similar techniques for calculating lattice constants developed independently by Hanford physicists and by a school of Russian physicists (as reported at the Geneva Conference). An estimate of maximum errors in f and η for thermal systems is described. Experiments and analysis thereof on … more
Date: December 7, 1955
Creator: Hanford Atomic Products Operation. Engineering Department. File Technology Section. Physics Research Sub-Section.
Partner: UNT Libraries Government Documents Department
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Prelimiary Analysis of the Plutonium Recycle Program Reactor Shield

Description: It is the purpose of this report to present the preliminary analysis of the PRPR shield. The results reflect a considerable degree of conservatism because of uncertainties that were present in the preliminary estimates of neutron and gamma fluxes incident on the shield.
Date: December 22, 1956
Creator: Wood, D. V. & Weeks, J. L.
Partner: UNT Libraries Government Documents Department
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