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SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Partner: UNT Libraries Government Documents Department
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A Possible Phase Transition in Liquid He3

Description: A possible phase transition in liquid He{sup 3} has been investigated theoretically by generalizing the Bardeen, Cooper, and Schrieffer equations for the transition temperature in the manner suggested by Cooper, Mills, and Sessler. The equations are transformed into a form suitable for numerical solution and an expression is given for the transition temperature at which liquid He{sup 3} will change to highly correlated phase. Following a suggestion of Hottelson, it is shown that the phase trans… more
Date: January 29, 1960
Creator: Emery, V. J. & Sessler, A. M.
Partner: UNT Libraries Government Documents Department
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Reactivity and efficiency trends vs operating trends for B, D, DR, and F Reactors, 1955--1959

Description: Changes in operation and corresponding changes in the reactivity status of Hanford reactors are the result of a continuing effort to improve operating efficiency. Trends data related to these changes in operation and reactivity have been published previously for the periods from 1950 through 1958. The purpose of this report is to include trends data for 1959. Bar graphs in the first part of the report show yearly averages of selected data, and tables in the last part of the report show maximum,… more
Date: April 29, 1960
Creator: Clark, D. E.
Partner: UNT Libraries Government Documents Department
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Production of cobalt-60

Description: Cobalt samples frequently are irradiated in nuclear reactors to produce gamma sources and can be irradiated as integral flux monitors because of the long half-life of the isotope produced. At the present time a small cobalt sample is being irradiated within the KW Reactor Snout facility for future use as a radiographic source for inspection of finished product in the Chemical Processing Department. Analysis was made to estimate the buildup of activity in this sample; the general equation may be… more
Date: February 29, 1960
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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KER-4 operating report test K-4-8, PT-IP-300-A

Description: Objective of the test was to determine and evaluate the behavior of 8 20-inch fuel elements during irradiation using the hot-headed end closures on the inner tube.
Date: December 29, 1960
Creator: Young, K. L.
Partner: UNT Libraries Government Documents Department
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Supplement D, Production Test IP-314-A, measurement of fuel element temperature changes as the result of film deposition

Description: The thermocouple train is modified by the substitution of one eighteen-inch enriched and four twenty-four inch natural uranium tubular elements for the two thirty-six inch enriched tubular elements used on the original thermocouple train. The operating limits for the loading have been changed because of the change in charge power. This supplement also authorizes the addition of fuel elements upstream of the thermocouple train if the thermocouple element and heater elements do not provide enough… more
Date: July 29, 1960
Creator: Kratzer, W. K. & Peacock, D. W.
Partner: UNT Libraries Government Documents Department
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Production test IP-376-D: Irradiation of MGCR-HDR-3 test element

Description: The objective of this test detailed in this report is to irradiate a test fuel assembly for the MGCR (Maritime Gas Cooled Reactor). The irradiation of this assembly will be carried out in the DR-1 Loop under controlled conditions to determine the feasibility of the heterogeneous 19-rod bundle fuel element concept. Diffusion of fission products through metal cladding. Fission gas retention of fuel bodies. Dimensional stability of fuel bodies, and satisfactory performance of the creep-shrink proc… more
Date: November 29, 1960
Creator: Bennett, E. C.
Partner: UNT Libraries Government Documents Department
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Possible causes of accelerated corrosion in the KER 1 loop

Description: The KER-1 Zircaloy process tube extracted from the reactor in May 1960, is currently being examined in Radiometallurgy with particular attention to an area of heavy oxidation and hydriding revealed during a burst test. The area in question is approximately 1 1/4in. wide and extends longitudinally an unknown distance from the points where sections have been taken. The oxide layer of interest is about 8 mils thick at the center, thinning at the edges. The ``oxide`` is quite adherent with only rel… more
Date: November 29, 1960
Creator: Dillon, R. L.
Partner: UNT Libraries Government Documents Department
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Reactivity in the centi-milli-K unit

Description: Tables present excess reactivity vs pile rising periods, excess reactivity vs pile falling periods, mint-nominal reactivity vs charge length, Pb-Cd nominal reactivity vs charge length, and nominal reactivity of poison splines.
Date: January 29, 1960
Creator: Clark, D. E.
Partner: UNT Libraries Government Documents Department
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IBM Problem M Curves

Description: Abstract: Presented here are working graphs of pressure, density, velocity, and temperature from the Los Alamos Scientific Laboratory calculations (IBM Problem M) of a spherically symmetric explosion in a homogeneous atmosphere.
Date: June 29, 1960
Creator: Broyles, C. D.
Partner: UNT Libraries Government Documents Department
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Structural Testing of SM-2 Fuel Elements

Description: Ability of the originally designed SM-2 stainless steel fuel elements to withstand static transverse pressure gradients of normal reactor operetion was investigated. Fourteen simulated original SM-2 type fuel elements by Tungsten inert gas (TIG) and electric resistance welding processes were subjected to pressure gradients to 6 psi and measured for deflection during stress and distortion after stress. Tests provided a basis for selecting a reference SM-2 fuel-element design and established a me… more
Date: September 29, 1960
Creator: Coleman, F.G. Jr. & Herbert, R.J.
Partner: UNT Libraries Government Documents Department
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Organic Compounds in Fission Reactors. [Part] 2. Thorio-Organic Compounds

Description: The advantages of the use of organic liquids in fission reactors to minmize corrosion and pressure problems were studied relative to the solution of thorium in such fluids. Thorio-organic compounds were prepared from organic acids, diketones, and other chelating compounds. Salts of carboxylic and phospho- organic acids were insoluble. The chelate with dibenzoylmethane was soluble in molten biphenyl but was decomposed at 300 deg C. The general low solubility of thorio-organic compounds in nonpol… more
Date: February 29, 1960
Creator: Baldwin, W. H.
Partner: UNT Libraries Government Documents Department
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Automatic Recording Unit

Description: From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.
Date: March 29, 1960
Creator: Ross, Frank A.
Partner: UNT Libraries Government Documents Department
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STABILITY OF UO$sub 2$-NaK SLURRIES. Final Report

Description: The UOsub 2/-NaK system was studied with special reference to the wetting of UO/dub 2/ by NaK and the effect of temperature on the viscosity of the UO/dub 2/-NaK slurry. It was found that UO/sub 2/ powder of approximately 1 micron average particle diameter was wetted by NaK at approximately 400 un. Concent 85% C. No evidence of dewetting or flocculation was noted at temperatures up to 600 un. Concent 85% C, although it was not proved conclusively flocculation does not occur at the higher temper… more
Date: March 29, 1960
Creator: Rymarz, T. M.
Partner: UNT Libraries Government Documents Department
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GAMMA AND BETA HEAT GENERATION RATES IN THE HFIR CORE

Description: A calculation was made to determine the fuel plate heat fluxes resulting from after shutdown fission product heating. Fission product source strengths were obtained via the IBM Internuc code. Slab geometry was assumed. The results indicated that the maximum heat flux would occur slightly inboard of the center of the fuel annulus, with the heat flux at the inner annulus radius running about 8% below the maximum, and the outer radius heat flux 10% below the maximum. For decay times of 1.0, 10, 10… more
Date: April 29, 1960
Creator: Hilvety, N.
Partner: UNT Libraries Government Documents Department
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Dry Bearing Endurance Test for the Service Machine: Experimental Gas-Cooled Reactor

Description: The concept of operating bearings and gears unlubricated in a helium environment was questioned as to fundamental soundness. Tests were made to determine if immediate gross failure occurs. A bearing of standard manufacture was operated in helium for 42 hr. A high degree of gradual wear was encountered. No gross or sudden failures were found. (W.L.H.)
Date: September 29, 1960
Creator: Flippen, B. H.
Partner: UNT Libraries Government Documents Department
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Solubilities of Selected Metals in Mercury: Hermex Process

Description: The solubilities of uraninm, thorium, gadelinium, sama rinm, and neodymium in mereury were determined from room temperatare to 356 deg C. Equations of the form log of solubility (wt.%) = a + b/T were developed for these metals. Integral heats of solution were calculated for each. The solubilities of ruthenium, palladium, zirconium, and molybdenum in mercury in the presence of excess uranium were determined; the low solubility of zirconium and molybdenum gave solutions with a concentration below… more
Date: June 29, 1960
Creator: Messing, A. F. & Dean, O. C.
Partner: UNT Libraries Government Documents Department
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Static Stress Determinations in Salt, Site Cowboy

Description: An investigation was made to determine the stress field in the salt dome and the stress concentrations on the surface of the small (12-ft diameter) sphere. For the most part, the apparatus and techniques used in the investigation are new and have not been described in other reports. Therefore the theory, concepts, apparatus, and some of the lists made to determine the reproducibility of the apparatus are described briefly. (W.L.H.)
Date: July 29, 1960
Creator: Merrill, Robert H.
Partner: UNT Libraries Government Documents Department
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