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Twin Channel Count Integrator (EH1-503)

Description: Report issued by the Brookhaven National Laboratory discussing a twin channel count integrator. As stated in the introduction, "an accurate and stable recording ratemeter, designed to present the data from two counters on one strip chart recorder, is described" (p. 1). This report includes tables, and illustrations.
Date: June 1956
Creator: Higinbotham, William A. & Tillinger, J.
Partner: UNT Libraries Government Documents Department

Summary Hazards Report on Enriched Fuel Element Loading for the BNL Research Reactor

Description: Report issued by the Brookhaven National Laboratory discussing a hazards report on replacing the research center's current fuel elements with new highly enriched elements. As stated in the introduction, "this report is a summary of the studies, both theoretical and experimental, which have been made so far of the nuclear properties of the "new" pile, of the stability of the new fuel elements, and of the safety and practicability of operation of the "new" pile" (p. 2). This report includes tables, and illustrations.
Date: May 24, 1956
Creator: Corngold, N.; Kaplan, I.; Chernick, J.; Gurinsky, D. H. & Fowell, R. W.
Partner: UNT Libraries Government Documents Department

Outlook and Research Possibilities for Bituminous Coal

Description: Report issued by the U.S. Bureau of Mines discussing research conducted on the bituminous coal industry in the United States. As stated in the introduction, "in addition to research and development work of the coal industry, that of associated industries and coal consumers is covered" (p. 1). This report includes tables, and illustrations.
Date: May 1956
Creator: United States. Bureau of Mines.
Partner: UNT Libraries Government Documents Department

National Motor-Gasoline Survey: Winter 1955-56

Description: Report issued by the U.S. Bureau of Mines discussing surveys conducted on the motor gasoline sold during the winter of 1955-1956. The amount, location, and price of gasoline sold during this time are presented. This report includes tables, illustrations, and a map.
Date: April 1956
Creator: Blade, O. C.
Partner: UNT Libraries Government Documents Department

Argonne National Laboratory Annual Report: 1956

Description: Report issued by the Argonne National Laboratory discussing the variety of work done at the laboratory during the year of 1956. This report includes tables, illustrations, and photographs.
Date: 1956
Creator: Argonne National Laboratory
Partner: UNT Libraries Government Documents Department

The Transient Behavior of Single-Phase Natural Circulation Water Loop Systems

Description: Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.
Date: March 1956
Creator: Alstad, C. D.; Isbin, H. S.; Amundson, N. R. & Silvers, J. P.
Partner: UNT Libraries Government Documents Department

The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350

Description: Report issued by the Argonne National Laboratory discussing the design and construction of equipment for reactor fuels. As stated in the summary, "the report describes the development, prototype construction, methods of testing, and leak detection of a modular hood design to be used in housing equipment and processes for the Argonne National Laboratory Fuel Fabrication Facility" (p. 9). This report includes tables, illustrations, and photographs.
Date: January 1956
Creator: Shuck, A. B. & Mayfield, R. M.
Partner: UNT Libraries Government Documents Department

Chrysotile-Asbestos Deposits of Arizona: Supplement to Information Circular 7706

Description: Report issued by the U.S. Bureau of Mines discussing asbestos mining and production in Arizona. As a supplement to a previous report, 18 additional Arizona mining districts are presented and described. This report includes tables, maps, illustrations, and photographs.
Date: May 1956
Creator: Stewart, Lincoln A.
Partner: UNT Libraries Government Documents Department

National Motor-Gasoline Survey: Summer 1955

Description: Report issued by the U.S. Bureau of Mines discussing surveys conducted on the motor gasoline sold during the summer of 1955. The amount, location, and price of gasoline sold during this time are presented. This report includes tables, illustrations, and a map.
Date: March 1956
Creator: Blade, O. C.
Partner: UNT Libraries Government Documents Department

Survey of Dust-Control Practices in the Coal-Mining Industry

Description: Report issued by the U.S. Bureau of Mines discussing dust-control of coal mining operations. As stated in the summary, "this circular presents results of a survey conducted by the Bureau of Mines to ascertain the extent to which dust-control practices are employed in the coal-mining industry" (p. 1). This report includes tables, illustrations, and photographs.
Date: April 1956
Creator: Barnes, R. W.; Gregory, M. J.; Owings, C. W. & Berger, L. B.
Partner: UNT Libraries Government Documents Department

MTR Technical Branch Quarterly Report, Third Quarter

Description: Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
Partner: UNT Libraries Government Documents Department

Preliminary report on development of coating for alloy case

Description: Coatings examined were selected industrial finishes reported to have good resistance to corrosion and included epoxy resins reinforced with fiberglass. For screening purposes,this preliminary work was done on commercial sheet Mg to which had been applied a dichromate finish. The coatings were tested for impact resistance, corrosion resistance, abrasion resistance, and thermal shock resistance. Conclusions for further work are outlined.
Date: July 27, 1956
Creator: Archibald, P.B.
Partner: UNT Libraries Government Documents Department

Neptunium-239 in disassembly basin water

Description: Since the presence of neptunium-239 in disassembly basin water had been suggested, analysis of the water was undertaken. The occurrence of Np-239 was thought to be due to its diffusion through the slugs. Samples of water from the D and E Canals in K and R-Areas were analyzed to determine the presence of Np-239. Samples from and K and R Areas both showed Np-239 to be present in quantities greater than 50% of the initial total activity.
Date: August 13, 1956
Creator: Carlton, W. H. & Boni, A. L.
Partner: UNT Libraries Government Documents Department

Danger Coefficient Measurements Using a Water Boiler Reactor

Description: The use of a water boiler reactor as a danger coefficient test instrument has been investigated, with emphasis on the testing of reactor materials for neutron absorbing impurities and the testing of uranium for enrichment variations. After calibration of the WBNS course control rod, tests were made on a variety of materials including beryllium, boron trifluoride, iron and steel, natural uranium metal and oxide, and uranium metal of various enrichments. Several experiments were conducted to evaluate the sources and magnitudes of errors in danger coefficient testing. On the basis of the data obtained from sample testing and auxiliary experiments, the sensitivity of the WBNS for absorption and enrichment testing was determined, as well as other constants relating to danger coefficient measurements. The Water Boiler Neutron Source has been found to be well suited to danger coefficient testing. Small absorption differences between samples of similar geometry and nuclear propenties can be determined to a standard deviation of 0.002 cm/sup 2/. The danger coefflcient technique using the WBNS compares favorably with other methods of absorption detecting methods, such as the shotgun test or chemical analysis. Enrichment differences between natural uranium samples of only 500 grams can be detected to plus or minus .0008 per cent U/sup 235/ by weight, and between 3 per cent enriched samples to plus or minus 0.0028 per cent U/sup 235/. In enrichment testing relative values can be found to an accuracy equivalent to those obtained from spectrographic analyses. With improvements in the WBNS core arrangement so that larger samples could be handled, and relocation of the glory hole to the flux center of the core, greater sensitivity could be obtained. The WBNS compares favorably to other reactors used for danger coefficient work (auth)
Date: March 1, 1956
Creator: Engholm, B.A.
Partner: UNT Libraries Government Documents Department

Sodium Graphite Reactor Quarterly Progress Report for October-December 1955. Section A. Section B

Description: An analysis was made of the nuclear parameters for sodium graphite reactor lattices. These parameters include thermal utilization, macroscopic cross sections, thermal diffusion length, and neutron absorption. Results of all calculations are given in graphical form. Test fuel slugs for the SRE were cycled up to 500 times between 100 and 500 deg C at the rate of 2 cycles/hr. Results are tabulated. The centrifugal casting of U alloy fuel slugs is briefly evaluated. Results of the microscopic examination of the extruded ThU breeder fuels are shown. The percent elongation of graphite due to the presence of Na is shown for various temperatures. Results of wear tests on graphite are also tabulated. The behavior of Zr in liquid Na was studied, and weight gains in Zr are summarized. Analog computer studies were continued, and data are included on the temperature effects of the response time of coolant channel Na outlet temperature thermocouples, the effects of continuous rod motion and pump speed changes on the outlet Na temperature and power, and the outlet temperature as a function of scram time. The critical evaluation of B--Ni rods is tabulated. The fuel rod assembly apparatus is described. Fuel rod development is discussed. Cyclograph traces of rods bonded with various Na--K alloys were recorded for rods at room temperature and heated to 450 and 600 deg F. The traces are indicative of uniform bonding. The moderator can fabrication and testing is also discussed. Tests were completed on Freeze Seal No. 2 for the 6-in. oval port Wedgeplug test valve at 450, 850, and 1250 deg F. The temperature gradients from the hot flange face to the end of the seal mechanism for various valve temperature conditions are shown. Sodium leak rates through the valve are tabulated. Progress in the development of a liquid Na ...
Date: April 15, 1956
Creator: Martin, A. B. & Cochran, J. C.
Partner: UNT Libraries Government Documents Department

Improvements to Task 1 and Task 2 234-5 Building

Description: In the P234-5 Building operation, Task I consists of converting plutonium nitrate solution received from the primary separations plants to a plutonium oxalate slurry. The slurry is filtered and the filter cake is transferred to Task II while the filtrate is treated and returned for further processing in either Recuplex, Redox, or Purex. The basic Task II process consists of calcining the plutonium oxalate cake to form plutonium dioxide. The plutonium dioxide is then fluorinated to form plutonium tetrafluoride which is transferred to Task III for further processing. Various alternate schemes for increasing production have been studied by the Technical and Design Sections during the past several months. The results of these studies are available in references (10) and (11). It is the purpose of this document to describe in detail the new equipment required for replacing Task I and II and to serve as a basis for detailed design of the proposed project.
Date: July 9, 1956
Creator: Fritz, J.R.; Yuenger, C.F. & Weeks, J.L.
Partner: UNT Libraries Government Documents Department