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A compilation of water temperatures near Grand Coulee Dam and in environs of Lake Roosevelt

Description: This tabulation of data collected since 1952 by the author was made in response to a request by the Atomic Energy Commission. It is understood it is to be transmitted to the Bureau of Reclamation for their information. The data are to afford basic information to support the Bureau`s decision in regard to a third power house at Grand Coulee Dam.
Date: January 31, 1962
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program Savannah I Fuel Irradiation Quarterly Progress Report October 1, 1961 - December 31, 1961

Description: This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the second quarter of fiscal year 1962. The data are summarized in Section II. Discussions on fuel performance, fuel environment (water chemistry), problems with loop operations, and the crud deposition program are included.
Date: January 31, 1962
Creator: Danielson, D. W. & Gilbert, R. S.
Partner: UNT Libraries Government Documents Department
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Model test of the inlet to K-Downcomer

Description: The existing K-Downcomer has the capacity for the new design flow rate, provided the temperature is limited. As the temperature increases, the entrance elbow commences to show cavitation and its capacity is greatly reduced. This capacity is not sensitive to flow rate, but is very sensitive to barometric pressure and the temperature of the flow. Flow as low, as 85,000 gpm exhibit the choking effect at approximately the same temperature as 20,000 gpm. Removal of the orifice plate and effluent bac… more
Date: January 31, 1962
Creator: Lomax, C. C. & Tinney, E. R.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Analog Simulator.

Description: The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; mo… more
Date: January 31, 1962
Creator: Crimmins, D. H.; Mohr, D. & Stone, J. T.
Partner: UNT Libraries Government Documents Department
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Production test IP-468-A-FP, Program for evaluation of alpha extruded fuel cores

Description: Currently, all normal production HAPO fuel cores are rolled into rods at Fernald, consequently, HAPO is dependent upon one vendor for a critical raw material. This arrangement does not appear to be consistent with good business practice, and it is desirable to have an alternate fuel source tested and available. Mallinckrodt`s Weldon Spring plant contains an extrusion press for the gamma bar extrusion and a logical sequence of operations should permit further extrusion in the alpha phase to the … more
Date: January 31, 1962
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, July 1961

Description: Thoria denitrator products from 0.04 to 0.066 N/Th ratio were dispersed into sols at N/Th radios of 0.11 to 0.19 and processed by the sol-gel technique to produce final compacted thoria products with little significant variation. Experimental results of H/sub 2/-CuO reaction in the helium purification work further substantiated the mathematical model. The elutions of uranyl sulfate loaded Dowex 2lK with chloride apparently involved the diffusion of both the sulfate ions and the uranyl ions. The… more
Date: January 30, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Characteristics of splines for fine distribution control

Description: The introduction of poison splines as operating aid at the Hanford reactors has resulted in an impressive production increase. This increase is mainly due to the effect on startup control and to better equilibrium flux shaping. In providing sufficient reactivity effect for startup control, however, present splines sometimes increase rather than decrease flattening and distribution control problems when utilized during equilibrium operation. In additional being of constant poison strength along … more
Date: January 29, 1962
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Hexafluorides of Molybdenum, Tungsten and Uranium. [Part[ 2. Reactions With Liquid and Gaseous Dinitrogen Tetroxide

Description: Molybdenum and tungsten hexafluorides form the solids nitrosylium pentafluoroxymolybdate(VI) and -tungstate(VI), respectively. Uranium hexafluoride gives nitrosylium hexafluorouranate(V) STANOUF/sub 6/!, the same salt that it forms with nitric oxide. (auth)
Date: January 29, 1962
Creator: Geichman, J. R.; Smith, E. A.; Swaney, L. R. & Ogle, P. R.
Partner: UNT Libraries Government Documents Department
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Physics aspects of operation in event of a large reactivity loss

Description: The following information was prepared to assist the physicist who encounters a large reactivity lass as in a water soaked lattice or a more permanent loss as in the case of balls remaining in the pile after a ball drop. The discussion is based on experience gained during F Reactor`s severe water leak of July 27, 1961.
Date: January 29, 1962
Creator: Heiple, R. B.
Partner: UNT Libraries Government Documents Department
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Proposal for charging the eighth fuel rupture experiment, GEH 10-57

Description: The objective of this test is to prove a new method of intentional rupturing of fuel elements under conditions of high specific powers and central core temperatures. The fuel will be the inner component of an NPR fuel element assembly. Permission to change one tubular fuel element (GEH-10-57) into the GEH-P7 loop is requested. A hydraulic cylinder will be attached to the fuel basket assembly. The hydraulic cylinder will be used to move a cutter along the outer surface of the fuel element. The c… more
Date: January 29, 1962
Creator: Kaulitz, D. C. & Call, R. L.
Partner: UNT Libraries Government Documents Department
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Recovery of Strontium and Rare Earths From Purex Wastes by Solvent Extraction

Description: A solvent extraction flowsheet was developed for recovery of strontium- 90 and mixed rare-earth fission products from adjusted Purex 1WW waste solution by di(2-ethylhexyl)phosphoric acid (D2EHPA) in Amsco l25-82 modified with tributyl phosphate (TBP). First cycle feed is prepared by adding tartrate and caustic to the waste solution to complex the iron and adjust the pH. Strontium and rare earths are coextracted with D2EHPA-TBP-Amsco and stripped with nitric acid in the first cycle, and then iso… more
Date: January 29, 1962
Creator: Wischow, R.P. & Horner, D.E.
Partner: UNT Libraries Government Documents Department
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Special Power Excursion Reactor Test III Pressurizer Vessel Failure

Description: Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
Date: January 29, 1962
Creator: Heffner, R. E.; Wilson, T. R.; Halls, D. P.; Hickman, W. W. & Hoopingarner, K. R.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-468-A-FP, program for evaluation of alpha extruded fuel cores

Description: The alpha phase extrusion of dingot bars to rods for core blank heat treatment at MCW offers a three-fold incentive, including: (1) establishment of an independent alternate source of uranium cores, (2) a slight cost improvement of MCW extrusion over FMPC rolling of dingot and (3) potential improvement in core quality and performance. The purpose of this test is two-fold: (1) to evaluate gross dimensional stability and (2) to evaluate the gross irradiation performance of alpha phase extruded di… more
Date: January 28, 1962
Creator: Clinton, M. A. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 2

Description: Twelve Zircaloy-2 clad UO/sub 2/ specimens, irradiated in the NRK to about 15,500 Mwd/t and decayed about 9 months, were declad and core dissolutions completed. The pellets were fractured brt were essentially intact (i.e. had not fallen apart) when declad. The U losses ramged from 0.03 to 0.09%, due to solubility of U(IV) in the Zinflex reagent, and the U losses from 0.01 to 0.04%. The core pellets were 99.5% dlssolved in 4 M HNO/sub 3/-0.1M Al(NO/sub 3/)/sub 3/ in 5 hr, which was slightly fast… more
Date: January 26, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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Production test IP-486-D, Irradiation of corrugated fuel elements

Description: The objective of this production test is to authorize the irradiation of three natural uranium corrugated I&E-type fuel elements in a KE Reactor front-to-rear test hole. The ultimate exposure of Zircaloy-2 clad, coextruded, uranium-cored fuel elements may be limited by localized tensile necking and splitting of the jacket. The total deformation capability of a fuel element is increased by corrugating the outside surface so the perimeter is greater than that of a circle circumscribing the equiva… more
Date: January 26, 1962
Creator: Marshall, R. K. & Kratzer, W. K.
Partner: UNT Libraries Government Documents Department
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Research Study on Neutron Interactions in Matter as Related to Image Formation

Description: Report discussing a study of various neutron image detector systems and their characteristics, and opal glass diffusers in an optical image synthesis apparatus. A five inch diameter neutron beam exposure facility is also discussed.
Date: January 26, 1962
Creator: Watts, H. V. & Terrell, C. W.
Partner: UNT Libraries Government Documents Department
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Dissociation and Ionization of H$Sub 2$$Sup +$ by Electrons and Protons

Description: <><DSN>16:009503<ABS>Included are summaries of studies of: DCX-1 operation and performance; DCX-2 design and engineering; plasma physics; vacuum arcs; ion production, acceleration, and injection; plasma theory and computations; magnetics; and vacuum system techniques. Separate abstracts were prepared for the eight sections. (B.O.G.) 9504(Faye unscannable abstract)
Date: January 24, 1962
Creator: Alsmiller, R. G., Jr.
Partner: UNT Libraries Government Documents Department
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PT IP-416 measurement of the horizontal rod strength at H Reactor. Final report

Description: The object of this test was to obtain data concerning the reactivity of the horizontal rods in the E-N fuel loading at H Reactor. An accurate calibration of the control rods could then be used to provide a more accurate measurement of the other reactivity variables associated with the E-N loading. A comprehensive rod calibration test was performed at H Pile in 1957. Results of the present test, needed because of the ``blacker`` E-N fuel in the pile, have been normalized to the 1957 test results… more
Date: January 24, 1962
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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