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OPERATING MANUAL FOR THE AE-6 REACTOR

Description: An attempt is made to provide a single reference source for material pertinent to the maintenance and operation of the AE-6 Reactor. Descriptions of various components are included, as well as the common operational and maintenance procedures and check lists. Information is given on the subcritical assemblies that may be studied. (W.D.M.)
Date: June 23, 1960
Creator: Moore, E.A. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

MATERIAL BUCKLING MEASUREMENTS ON GRAPHITE-URANIUM SYSTEMS AT HANFORD: A SUMMARY TABULATION

Description: Measurements of material bucklings for graphite uranium systems are summarized. A comprehensive listing and guide to the original data sources is provided. Complete information on physical and nuclear properties of the lattice and the geometry of the exponential assembly is included, along with some of the auxiliary data taken. The fuel sizes vary from 0.925 to 2.5 in. in diameter for five different fuel geometries. The lattice spacings vary from 4 3/16 to 15 in. Over 300 measurements of material buckling are included. (auth)
Date: May 1, 1961
Creator: Wood, D.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

STRUCTURAL ANALYSIS OF ZIRCALOY FUEL-ELEMENT CONTAINERS FOR THE NS SAVANNAH REACTOR

Description: Structural evaluations were made of the 15% cold-worked Zircaloy fuel- element containers proposed for the NS Savannah reactor. These evaluations, which are consistent with the Navy Code, permitted the sizing of components so that under conservative loading conditions both stress and deflection limitations would be met. The necessary design modifications were specified for the fuel- element container assembly. (auth)
Date: August 19, 1963
Creator: Shobe, L.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

THERMAL UTILIZATION MEASUREMENTS WITH U-10 Mo FUEL IN THE HALLAM EXPONENTIAL LATTICES

Description: A description is given of measurements required to determine the values of thermal utilization for U-10 wt.% Mo fuel elements in hexagonal lattices of three different spacings. The discussion includes a description of the lattice cells, and a graphical representation of the neutronflux distributions in the cell materials. Epi-cadmium neutron-flux distributions and cadmium ratios for each lattice cell studied are included. (auth)
Date: December 19, 1960
Creator: Hillig, O.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

BORAX V EXPONENTIAL EXPERIMENT

Description: The cadmium ratio was measured in an exponential mockup of Borax V as a function of the void fraction. The extent of voids, simulated by lengths of closed polyethylene tubes, ranged from 0 to 40%. The corresponding cadmium ratios ranged from 6.1 to 4.6. The exponential was also used to determine the radial flux pattern across a Borax-type fuel assembly and the fine flux detail in and around fuel rods. For a normal loading the maximum-to-average power generation across an assembly was 1.24. (auth)
Date: April 1, 1963
Creator: Kirn, F.S. & Hagen, J.I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

NUCLEAR ENGINEERING LABORATORY WITH A POINT NEUTRON SOURCE

Description: The equipment necessary for a nuclear engineering laboratory wtth a point neutron source is discussed. Some general references on neutron work are listed. Experiments are outiined which use a neutron howitzer, a tank of water, a sigma pile, and a natural U and graphite exponential pile. (M.H.R.)
Date: March 17, 1958
Creator: Pomerance, H.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department

Some Nuclear Experiments on the SRE

Description: Subcritical assembly experiments were conducted by loading fuel elements in a SRE core and determining the critical mass from the counting rate data obtained from fission counters placed in the fuel channels. A plot of the normalized inverse count rate as a function of the number of the fuel elements loaded indicated a critical mass of 22.2 dry fuel elements at room temperature and 32.64 plus or minus 0.10 fuel elements at 400 deg F using a sodium coolant. The reactivity of the subcritical SRE was estimated from subcritical multiplication measurements, and the results were used to evaluate the worth of various fuel elements and poison elements. The total reactivity change caused by replacing each uranium element with a thorium-5% uranium element was determined. Flux mapping studies were made of the dry subcritical SRE using cadmium-covered and bars gold foils in the core and reflector. The results of the flux msasurements are given graphically. (B.O.G.)
Date: June 1, 1957
Creator: Guderjahn, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department