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HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date: February 1, 1961
Creator: Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner: UNT Libraries Government Documents Department
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SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS

Description: Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high frequency resistance welding processes were also applied to molybdenum alloys. The oxidation of molybdenum, tantalum, and niobium in flowing air at 2000 deg F is also given. (P.C.H.)
Date: February 10, 1961
Creator: Thompson, E.G.
Partner: UNT Libraries Government Documents Department
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Tertiary Blast Effects: The Effects of Impact on Mice, Rats, Guinea Pigs and Rabbits. Technical Progress Report

Description: A total of 455 mlce, rats, gulnea plgs, and rabbits was subjected to lmpact at velocitles ranglng between 25 ft/sec and 51 ft/sec. The deslred velocities were generated by allowlng the anlmals to free-fall from various helghts to a flat concrete pad. The ventral surface of each anlmal was the area of impact. Problt analyses of the 24-hr mortallty data ylelded LD/sub 50/ lmpact veloclties with 95% confldence limits as follows: mouse, 39.4 (37.4 to 42.0) ft/ sec; rat, ft/sec; and rabbit, 31.7 (30.2 to 33.3) ft/sec. The LD/sub 50/ figures for the mouse and rat were slgnificantly higher, statlstically, than those for the gulnea plg and rabblt. The small spread ln the LD/sub 50/ values suggested little variation ln the tolerance of blologlcal systems to impact. Further, the steepness of the mortallty curves lndicated a narrow survlval range to lmpact. Extrapolatlon of the experimental data to the 70 kg anlmal yielded a predicted LD/ sub 50/ impact velocity of 26 ft/sec (18 mph). Literature relevant to the human case was revlewed and the tentative appllcabllity of the predlcted flgures to adult man ls discussed. (auth)
Date: February 28, 1961
Creator: Richmond, D. R.; Bowen, I. G. & White, C. S.
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments. Experimental Program, Experimental Procedures and Safety Considerations

Description: Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described. (M.C.G.)
Date: February 1, 1961
Creator: Kock, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
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Isotopic Sources of Secondary Radiation. Final Report

Description: Recent work on isotopic x ray sources is reportcd. The research was directed toward optimization of high-level isotopic sources and evaluation of their use in typical scientific and technical applications. The resulting experi- mental data are used in obtaining an approximate mathematical formulation of x- ray output as a function of beta energy, target mnaterial, and source configuration. (J.R.D.)
Date: February 1, 1961
Creator: Filosofo, I.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF METHODS FOR THE REFABRICATION OF EBR-II FUEL ELEMENTS. PART I. ENGINEERING CONSIDERATIONS FOR EBR-II FUEL REFABRICATION. PART II. DEVELOPMENT OF INJECTION CASTING METHODS AND EQUIPMENT. PART III. DEVELOPMENT OF FUEL PIN PROCESSING METHODS AND EQUIPMENT. PART IV. ASSEMBLY, WELDING, AND LEAK TESTING EBR-II FUEL RODS. PART V. DODIUM BONDING AND BOND TESTING EBR-II FU

Description: The development of remote fabrication methods and equipment in which the cooling periods, chemical fission product separation, and complete decontamination of the fuel is not required is discussed. A process designed around precision casting in multiple, glass molds served as a basis for design of refabrication equipment. The injection casting process is used. Procedures and equipment were developed for the remote manufacture of right-cylindrical, uranium alloy fuel pins from the castings. Assembly, welding, and leak testing of the EBR-II fuel rods are described. Methods of sodium bonding and bond testing are described. (M.C.G.)
Date: February 1, 1961
Creator: Shuck, A.B.; Ayer, J.E.; Jelinek, H.F.; Iverson, G.M.; Carson, N.J. Jr.; Brak, S.B. et al.
Partner: UNT Libraries Government Documents Department
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Synthesis and Fabrication of Refractory Uranium Compounds. Summary Report for May 1959 Through December 1960

Description: Activitiee are described in an investigation to develop refractory U materiala for superior reactor fuels. Uranium carbide was prepared by cold pressing in pellets with densitier of 92 to 96% of theoretical. Uranium nitride was synthesized, and it was found that dense specimens (95% of theoretical) could be obtained in N-deficient powder, however in stochiometric compositions the maximum density obtained was 85% of theoretical. In other work dense uranium silicide was prepared and several properties of UC, UN, and U/sub 3/Si/sub 2/ were studied. (J.R.D.)
Date: February 1, 1961
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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Equations of State for Evolution Studies of Supernovae

Description: Tables of the energy, pressure, and chemical composition for a stellar mixture, originally a pure Fe/sup 56/, are presented as functions of temperature and density. They cover a range of conditions pertinent to the evolution of supernovae, involving the deconiposition of iron into helium plus neutrons, and the later stage of decomposition of helium into neutrons and protons. Relativistic degeneracy of electrons is included in these calculations. (auth)
Date: February 1, 1961
Creator: Grasberger, W. H. & Yeaton, J. B.
Partner: UNT Libraries Government Documents Department
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THE HEAT TREATMENT OF PLUTONIUM

Description: Two groups of plutonium bars, one group containing 165 ppm iron and the other 678 ppm iron were end-quenched from the beta, gamma, delta, delta-prime, and epsilon phases. In general, cooling rate was found to have three striking effects on microstructure. The alpha grain size was found to decrease with increasing cooling rate during cooling from all phases. Upon cooling high-iron plutonium from the epsilon phase, the size of the Pu--Pu6/sub 6/Fe eutectic network decreased with increasing cooling rate. Cooling high-iron plutonium from temperatures between 413 and 460 deg C produced a wide variety of Pu --Pu/sub 6/ Fe configurations in the microstructure. Finally, the size of an unidentified spheroidal inclusion, soluble in the delta and higher temperature phases, decreased as cooling rate increased across the delta to gamma transformation. These effects of cooling rate can be used to indicate the cooling rate or thermal history that a particular plutonium specimen has encountered. A linear relationship between the alpha grain size and the Pu--Pu/sub 6/Fe eutectic network size was observed. The network size was roughly two times larger than the alpha grain size. Hardness traverses on each of the bars indlcated no apparent effect of coollng rate during quenchlng on hardness. A density decrease was noted near the quenched end of both low and high-iron bars which lndicated that faster cooling rates promote microcracklng. However, a greater decrease in density was obtained for the low-iron bars which was attributed to their greater tendency to microcrack. The presence of the Pu--Pu/sub 6/Fe eutectic network in the high-iron bars inhibits microcracking. (auth)
Date: February 1, 1961
Creator: Gardner, H.R.
Partner: UNT Libraries Government Documents Department
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PHASE I REPORT OF DEVELOPMENT TECHNIQUES FOR POWER PRODUCTION FROM MIXED FISSION PRODUCTS

Description: An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development eIforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, ldaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes. Bulk densities of 0.8 g/cc were increased to 2.9 g/cc by selective use of fluxes and cold compacting techniques. This means that power densities of up to.001 w/cc will be possible from waste materials in the ldaho Chemical Processing Plant tanks. An experimental program for the evaluation of the high temperature life characteristics of bismuth telluride alloys is discussed. A program for the optimization of thermoelectric convertor design utilizing the diffuse heat from a mixed fission product source is described, derivation of pertinent equations are presented and results of the study are discussed. Conceptual designs for thermoelectric generators utilizing diffuse fission product heat sources are described. Problem areas regarding the use of mixed fission products in conceptual thermoelectric conversion device designs are discussed, with particular emphasis being placed on …
Date: February 18, 1961
Creator: Eaton, D.
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 13, Number 6, February 1961

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: February 1961
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Description: Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.
Date: February 15, 1961
Creator: Alco Products (Firm).
Partner: UNT Libraries Government Documents Department
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Fission Product Activity in SM-1 Core I Primary System and Surface Contamination on SM-1 Type Fuel Elements. Task XVIII, Phases 2 and 3

Description: Abstract; The fission product data obtained during SM-1 Core I operation (June 1957 - May 1960) is reviewed briefly and interpreted. Evidence is presented to indicate that a fuel element defect was responsible for the high fission product activity level observed in the primary coolant. Relative escape coefficients are calculated and the defect size estimated. Anticipated fission product levels during SM-1 Core II and SM-1A Core I operation are estimated from alpha surface contamination data on completed fuel elements. The importance of in-line sampling for monitoring fission product activity is stressed as well as the need for failed fuel element detection methods.
Date: February 28, 1961
Creator: Hasse, Robert A. & Zegger, John L.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.
Date: February 20, 1961
Creator: Agar, J. D.
Partner: UNT Libraries Government Documents Department
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Evaluation of the Fallout Protection Afforded by Brookhaven National Laboratory Medical Research Center

Description: Report regarding an experimental study to determine how much protection the Medical Research Center at Brookhaven National Laboratory provided against nuclear fallout. Fallout was simulated by pumping a sealed source of Co60 through tubing.
Date: February 1961
Creator: Borella, H.; Burson, Z. & Jacovitch, J.
Partner: UNT Libraries Government Documents Department
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E-N and blanket conversions from analysis of tubes irradiated at H

Description: A block-loading of striped columns and tubes simulating a blanket loading were analyzed for product (Pu, tritium, E-metal) after irradiation in IP-255-A-9-FP. Results are rationalized to full-pile values; pile conversion ratios and pile gains are given.
Date: February 10, 1961
Creator: Lang, L. W. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-310-A-FP, determination of the dimensional stability of uranium fuel cores classified by the fuel core tester (UT-2)

Description: The objectives of this test are: 1. To establish grain size limits for acceptable uranium fuel element cores. 2. To establish, if possible, criteria for predicting core dimensional stability during irradiation by comparing the relative dimensional stabilities associated with grain size and with variations in grain size in individual cores. 3. To obtain process tube and fuel corrosion data associated with bumper fuel elements in new tubes with no mixer, one mixer in the 10th position and two mixers in the 7th and 15th position from the rear. Fuel cores representing the full range of UT-2 voltage values (grain size converts to d-c voltage) of interest are segregated into three categories: a. Large grains. b. Variations of grain size in an individual core. c. Small grains. Each category will be subdivided into three groups, each covering a small range of values. After canning, the finished fuel elements will be assembled into twenty-seven (27) charges in three latin square patterns for irradiation to a 900 MWD/T exposure goal in D Reactor.
Date: February 15, 1961
Creator: Hodgson, W. H. & Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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A standard AlSi braze wetting test for aluminum components used in the lead-dip process

Description: Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting potential of aluminum components used in the lead-dip process, and to provide a tool for measuring the acceptability of aluminum components for the preparation of fuel elements.
Date: February 1, 1961
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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