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Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963

Description: From abstract: The concept of using high intensity beta radiation from an isotopic source, Sr-90, inside a high temperature, high pressure chemical reactor has been developed for potential radiation chemical processes. Distinct advantages include high utilizable intensity from a relatively small source with a minimum of shielding against external radiation.
Date: September 11, 1964
Creator: Yavorsky, P. M. & Gorin, E.
Partner: UNT Libraries Government Documents Department
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Annual progress report of the U. S. C. Nuclear Physics Research Laboratory supported by US Atomic Energy Commission. [Dept. of Physics, Univ. of Southern California, 1964]

Description: Operation of the present accelerator is summarized and plans for a new injection system and additional machine modernization are described. Research results of both experimentalists and theorists are reviewed in very brief summaries; references are provided. (RWR)
Date: September 1, 1964
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department Monthly Report: August 1964

Description: This report, for August 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: September 21, 1964
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
Partner: UNT Libraries Government Documents Department
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241-SX tank farm waste storage

Description: Salt wastes from the Redox solvent extraction process have been routed to the 241-SX tank farm for storage since May 21, 1954. Tanks in this farm contain wastes from three types of irradiated uranium processing: (1) low (approximately 250 MWD/T) and (2) high (approximately 600 MWD/T) natural uranium; and (3) E-metal. It is estimated that approximately 1.6 Kgs of Am-Cm, 17 Kgs of Np-237, 20 Kgs of Pu and 8 tons of uranium are present in the sludges from wastes generated through 4-30-64. A total … more
Date: September 3, 1964
Creator: Hanson, G. L.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories monthly activities report, August 1964

Description: The monthly report for the Hanford Laboratories Operation, August 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics, and programming operations are discussed.
Date: September 15, 1964
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department 200 West Area Tank Farm Inventory and Waste Reports

Description: This document lists all tanks which were active during each month by Waste Farm, which includes all tanks to which additions or subtractions were made. Each type of waste was indicated in each case, along with the nature of transfer and any pertinent remarks. Also reported are gallonage and inches of liquid in each tank.
Date: September 9, 1964
Creator: Bayless, M. K.
Partner: UNT Libraries Government Documents Department
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Swelling behavior of co-product driver elements: KER test K-3-19

Description: This interim report details the irradiation testing of co-product fuel-target assemblies in KER loops 3 and 4 which was authorized by PT-IP-645-D. The purpose was to demonstrate and characterize the simultaneous generation of plutonium and tritium during the irradiation of simulated N-Reactor co-product assemblies. Thirteen assemblies, each consisting of a 1.25% enriched outer fuel or driver tube and an inner, coaxial, lithium bearing target rod, were loaded in KER-3 and irradiated to approxima… more
Date: September 23, 1964
Creator: Goffard, J. W.
Partner: UNT Libraries Government Documents Department
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Swelling behavior of KSE-5 fuel elements: KER test K-2-21, Interim report

Description: This report discusses the irradiation testing of thick-walled single-tube, 1.6% enriched test elements (KSE-5`s) in KER loops 1 and 2 to evaluate swelling behavior of uranium at high temperatures. Test charge K-2-21 consisted of four KSE-5`s containing uranium with 400 ppm iron and 800 ppm aluminum. The object of the test irradiation was to establish the swelling performance of the fuel containing the iron-aluminum additions using the N-fuel composition as a reference fuel. This latter fuel has… more
Date: September 23, 1964
Creator: Goffard, J. W.
Partner: UNT Libraries Government Documents Department
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Proposal: Direct ingoting of unpickled buttons for economic and product quality gains

Description: The final product from the Reduction Operation at the present time is an unalloyed button of reasonably high purity and density. Considerable effort is being directed toward improvement of button purity and surface finish, or appearance. A direct ingoting step is proposed in place of button pickling as a practical means of improving metal quality and appearance. A second ingoting step is proposed to further improve process economics through improved radiographic integrity. Ingoting of buttons i… more
Date: September 21, 1964
Creator: Bond, R. H.
Partner: UNT Libraries Government Documents Department
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Fabrication of hot die sized diffusion bonded fuel elements from oil and water quenched cores for production test IP-708-A

Description: The hot die sizing (HDS) process is being considered as a replacement for the existing AlSi brazing process. Fuel cores are clad by passing a preheated core-component assembly through a die to bond the outside surface. Concurrently, the assembly is passed over a die plug to bond the internal surface. End bonding is accomplished in a following step by applying heat and pressure to the sized fuel element. Remaining fabrication steps are essentially the same as those used for AlSi brazed fuel. Ini… more
Date: September 15, 1964
Creator: Strand, C. A.
Partner: UNT Libraries Government Documents Department
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Defect test of target component of co-producer test element

Description: Irradiation tests of aluminum-lithium co-producer target elements are planned for charging in the N-reactor. Although the target elements are subjected to extensive non-destructive testing to assure that defective pieces are not charged, it is necessary to have some knowledge of the failure characteristics of the targets under reactor conditions. To study the possible behavior of in-reactor failures, a series of defected test elements were tested in the high temperature, pressurized TF-9 facili… more
Date: September 1, 1964
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Activity of irradiated regular metal in buckets

Description: The potential of shipping a bucket of metal that has not had sufficient decay time is a common problem to all Reactor Processing Operations. The only method at present to assure shipping adequately decayed metal is by procedural control. This study was performed to determine the feasibility of establishing decay time for irradiated metal in buckets by radiation activity measurements.
Date: September 14, 1964
Creator: Smith, R. H.
Partner: UNT Libraries Government Documents Department
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Effect of horizontal control rods in total control compensation

Description: This document provides a method for calculating the compensating effects of horizontal control rods in highly shadowed cases encountered in total control administration. The two-dimensional diffusion theory computer code ``9 ANGIE`` was used to calculate the reactivity effects of the horizontal control rod geometry with respect to total control requirements at B, D, F, and DR Reactors. For total control requirements in the center section of B, D, F, and DR Reactors the horizontal control rods w… more
Date: September 4, 1964
Creator: Vaughn, A. D.
Partner: UNT Libraries Government Documents Department
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Improved neptunium accumulation flowsheet

Description: The Redox acid precycle flowsheet which has been in use since November of 1959 vas adopted to provide neptunium recovery. Although neptunium recovery on this flowsheet has been satisfactory, several problems have been encountered. Among these are: marginal uranium decontamination, increased hexone degradation and increased corrosion of precycle piping and equipment. To circumvent these problems an acid-deficient precycle flowsheet was proposed. In August, 1964, following replacement of the 1A C… more
Date: September 3, 1964
Creator: Isaacson, R. E.
Partner: UNT Libraries Government Documents Department
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Swelling behavior of KSE-5 fuel elements; KER Test K-1-22: Interim report

Description: Production Test IP-544-A authorized the irradiation testing of coextruded Zr-2 jacketed, single tube, thick walled, 1.6 percent enriched tubular elements (KSE-5`s) in KER loops 1 and 2 to evaluate swelling behavior at high uranium temperatures. This PT was intended to permit the evaluation of uranium swelling at N-reactor environmental conditions but at considerably higher uranium temperatures than those occurring in N-reactor fuel. Evaluation of the fuel performances at the authorized maximum … more
Date: September 23, 1964
Creator: Goffard, J. W.
Partner: UNT Libraries Government Documents Department
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The use of chemical additives to improve first cycle decontamination at Purex

Description: The decontamination cycle (HA) at Purex has occasionally responded favorably to additions of waste rework material. The effect, exhibited in increased extraction of plutonium and improved decontamination from fission products has become known as the ``Tonic effect.`` Efforts to find the agent or agents in waste rework which are responsible for this effect have not been successful. Workers at ORNL, principally C. A. Blake, found that various materials decreased the distribution ratios of zirconi… more
Date: September 25, 1964
Creator: McKenzie, T. R.
Partner: UNT Libraries Government Documents Department
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Outline: N-Reactor capability report

Description: The flexibility of N-Reactor will be demonstrated by comparing (in tabular form) the basic 4000 Mw Pu-only, weapons grade case with a 4800 Mw co-product, weapons grade mode including production of Po-210 and PU-238. The competitive position of N-Reactor in the AEC complex will be illustrated in a table summarizing 1964 production studies.
Date: September 1, 1964
Creator: Dickeman, R. L.
Partner: UNT Libraries Government Documents Department
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Re-entry Flight Demonstration Number One (RFD-1): Data Book

Description: Re-entry flight demonstration number one (RFD-1) was launched on May 22, 1963 from the Scout launch complex at NASA Wallops Station, Wallops Island, Virginia.
Date: September 1964
Creator: Erickson, C. E.
Partner: UNT Libraries Government Documents Department
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Re-entry Flight Demonstration Number One (RFD-1): Preflight Disassembly Analysis and Observed Disassembly of the Simulated SNAP-10A Reactor

Description: Abstract: This report describes the SNAP-10A Simulated Test Reactor, the test philosophy of Re-entry Flight Demonstration Number One, the analytical analysis of reactor disassembly, and the results of the flight test.
Date: September 1964
Creator: Klett, R. D.; Hysinger, T. M. & Robertson, M. M.
Partner: UNT Libraries Government Documents Department
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Irradiation analysis, production test IP-672, HAPO 238, irradiation of impacted UO{sub 2}-PuO{sub 2} fuel rod bundles in C reactor

Description: The loss of flow is considered as far as the flow to the inlet hydraulic connector, inlet plugging and water shutoff time. A mockup revealed no vibration of the fuel element bundles and at the low temperatures present there should be no problem of corrosion. Efforts to assure safety with plutonium in the fuel elements are noted. (GHH)
Date: September 14, 1964
Creator: Cox, J. H.
Partner: UNT Libraries Government Documents Department
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Hydraulic supply and demand characteristics of thorium target elements in B, C, D, and K process tubes

Description: In conjunction with the proposed thorium target element replacement program, hydraulic tests were performed in the Hydraulics Laboratory in 185-D building to determine the flow characteristics of 1.480-inch OD solid thorium loadings in B, C, D, and K fringe tubes. Included are supply curve data for those orifice combinations which are tentatively to be used with the thorium loads in the various fringe tubes. In addition, predicted supply-demand characteristics are presented for a loading of 1.6… more
Date: September 15, 1964
Creator: Angle, C. W.
Partner: UNT Libraries Government Documents Department
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