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The Diffusion of Hydrogen in Zirconium Hydride

Description: The diffusion of hydrogen in zirconium hydride was studied using permeation techniques. The rate of permeation of hydrogen through zirconium hydride disks was measured for small concentration gradients. Data were obtained at 61 to 65 at.% hydrogen and 500 to 750 ction prod- C. The diffusion coefficients were determined by the time-lag method. Ho variation of the diffusion coefficients with hydrogen concentration was observed. The diffusion coefficients can be expressed by D (cm/sup 2/ per sec) = 599 exp (-34,800/RT). (auth)
Date: March 1, 1960
Creator: Albrecht, W. M. & Goode, W. D., Jr.
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 12, Number 7, March 1960

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: March 1960
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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An assessment of the zirconium tube program -- C Reactor pilot demonstration installation

Description: Production Test IP-272-A-FP authorizes the installation of up to 100 smooth bore Zircaloy-2 process tubes in C Reactor to demonstrate the feasibility of self-supported fuel elements for production use. An additional 200 zirconium tubes are expected to be delivered by mid-year and con be used to expand the initial demonstration facility. It is the purpose of this document to assess the status of the pilot demonstration program from the B-C Reactor Operation viewpoint.
Date: March 18, 1960
Creator: Amy, G. O.
Partner: UNT Libraries Government Documents Department
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Halogen Collector Test Program

Description: Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
Partner: UNT Libraries Government Documents Department
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Fast Reactor Core Design Parameter Study

Description: Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date: March 1960
Creator: Atomic Power Development Associates
Partner: UNT Libraries Government Documents Department
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Consolidated Edison Thorium Reactor Physics Design

Description: The nuclear characteristics of the CETR are described. Core operating lifetime, control-rod worth, and powerdensity distribution are discussed in relation to maximizing the core operating life. Other objectives of nuclear design are to minimize the power-density variation and to assure control of the reactor. (J.R.D.)
Date: March 1, 1960
Creator: Barringer, H. S.; Flickinger, R. B. & Spetz, S. W.
Partner: UNT Libraries Government Documents Department
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Piping Changes for Increased Production at B, D, DR, F, C and H Reactors calculations

Description: On January 22, 1960, HW-63487 Piping Changes for Increased Production at B, D, DR, F, C, and R Reactors, was published. This study investigates the valve pit piping, front and rear face piping,and effluent lines between the 105 Buildings,and the retention basins to determine modifications necessary to increase power levels in the 100-B, D, DR, F, C, and H Areas by increasing either or both temperatures and flows. The study was based on detailed hydraulic and stress calculations of the existing and proposed piping systems which because of their detailed and voluminous nature were not included in the study. It is the purpose of this study to document, in so far as possible, these calculations together with pertinent information which was not included in the original study.
Date: March 24, 1960
Creator: Bauer, G. H.; Harrison, C. W.; Hill, V. R.; McLenegan, D. W. & Mondt, J. F.
Partner: UNT Libraries Government Documents Department
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THE BMI-16 RECIRCULATING GAS LOOP INSTALLED AT THE ETR

Description: A developmental program was conducted to provide and in-pile loop facility for use in evaluating gas-cooledreactor fuel asubassemblies. The program included the design, construction, and installation of a recirculating gas loop which is located in a 6 by 6-in. facility in the aluminum reflector of the ETR. The loop system was designed to recirculate the primary nitrogen coolant at flow rates up to 0.9 lb per sec and pressures up to 200 psia. It will accept fuel subassmeblies up to 36 in. in length and 2.26 ia. in diameter with specimen power generation up to 150 kw. The maximum coolant temperature at the specimen outlet is set at 1500 deg F. The loop system includes the in-reactor section, the machinery, the control system, and the specimen-handling apparatus. Salient features of the re-ertrant system include an aluminum pressure wall in the in-reactor section, static gas insulation between the reactor coolant and the circulating loop gas, and a controllable rate of heat exchange between the specimen inlet- and specimen outlet-gas channels in sections of concentric countedlow piping. The three blowers in the system feature grease-lubricated bearings and water cooling. The complete system was tested out of pile and is now installed in the ETR. (auth)
Date: March 18, 1960
Creator: Baum, J. V. & Francis, G. A.
Partner: UNT Libraries Government Documents Department
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SELECTION OF THE PIQUA OMR FUEL ELEMENT

Description: Two types of aluminum-clad uranium alloy fuel elements, a square (parallel flat plate) and a circular (concentric cylindrical shell) were investigated to determine their relative suitability for use in the Piqua Reactor. Nuclear, thermal, and mechanical data are given, and considerations leading to selection of the circular element are presented. Design dimensions are listed and reactor thermal design and operating conditions are given for the proposed element. (auth)
Date: March 15, 1960
Creator: Baumeister, E.B. & Wilde, J.D.
Partner: UNT Libraries Government Documents Department
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Travel to Oak Ridge and Savannah River Plant to Study Processing Plant Containment Philosophy. Trip Report, January 26--29, 1960

Description: This report discusses travel to the Oak Ridge National Laboratory on January 26 and 27 and the Savannah River Laboratory and Plant on January 28 and 29, 1960. The primary objectives of the trip were to obtain information on the containment philosophy for processing plants recently adopted by Oak Ridge National Laboratory and on the Palm Program at Savannah River.
Date: March 9, 1960
Creator: Beard, S. J. & Oberg, G. C.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section B Monthly Progress Report, March 1960

Description: Consolidated Edison type fuel pellets were irradiated and analyzed, to determine the extent of fracturing, particle size of fines produced, and the rate of dissolution in boiling 13M HNO/sub 3/-0.04M NaF -0.1M Al(NO/sub 3/)3. Fused sodium or potassium hydroxide was used to shatter the pellets at 400 deg C or higher. Similar pellets were dissolved in H/sub 3/PO/sub 4/ and fused ammonium bifluoride. An investigation was made of the thermodynamics and limits of flammability of gases expected during the dissolution of sodium-bonded stainlesssteel-clad fuels in aqua regia or sulfuric acid. The amount of hydrogen evolved during Darex dissolution of 304 stain less steel was studied as a function of the fraction of total dissolving time and the total gas evolved. The rate of dissolution of tin in HF containing H/sub 2/O/sub 2/ was> 10 mg/cm/sup 2/- min at 13 to 72 deg C, but decreased> 10 times at 13 deg C when HF was replaced by NH/sub 4/F. A technique was developed for disintegrating and leaching graphite fuels, which yielded a recovery of 99.85% + uranium from fuels containing approximately 5% uranium. The uranium extraction in the Immi hot- cell facility indicated a 0.33% loss in the mixer-settler using the 6% TBP flowsheet. Yankee Atomic fuel, containing a fissia concentration of 10,000 Mwd/ T uranium, was dissolved by the Darex and Sulfex Processes to determine the amount of acid insoluble residues formed. Solvent extraction studies revealed that thorium and uranium could be costripped from a 30% TBP neutral solution with Al(NO/sub 3/)/sub 3/. Distribution coefficients were determined for thorium and uranium in 30% TBP-Amsco systems. The presence of H/sub 2/O/sub 2/ in Zirflex dissolver solutions was found to decrease the corrosion rates of Hastelloy F, type 309 stainless steel, and Ni-o-nel. Palladium-titanium alloys showed somewhat higher corrosion rates than Ti-45A …
Date: March 1, 1960
Creator: Blanco, R E
Partner: UNT Libraries Government Documents Department
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REDUCTION OF CUPRIC OXIDE BY HYDROGEN. I. FUNDAMENTAL KINETICS

Description: Basic studies of the kinetics of the reduction of copper oxide were made to establish the effect of the solid phase on the over-all reaction kinetics The reaction CuO + H/sub 2/ at the only rea Cu + H/sub 2/O consisted of an induction stage, an acceleration or autocatalytic stage terminating at about 35% reduction of the exide, and a decreasing-rate stage The reduction rates for each stage were dependent on the nature of the initial oxide, the degree of subdivision of the oxide, and the temperature but were independent of the mass of the oxide phase. Addition of the reaction product copper had no measurable effect on the reaction. Water vapor in concentrations of 25 mg per liter of H prevented reduction at 112 ction prod- C The inhibiting effect decreased rapidly as the temperature was increased and disappeared entirely at 190 ction prod- C. Once reduction bad started. water vapor had practically no effect The acceleration and decay stages were very closely approximated by a semiempirical equation based on the initial reaction occurring on certain active nuclei followed by a rapid growth of these nuclei by a branching-chain mechanism. The reduction rate reached a maximum and subsequentlv decreased as considerable interference occurred among the branching nuclei. Arrhenius plots gave an activation energy- of 13.5 plus or minus 1.2);cal for the reduction. (auth)
Date: March 30, 1960
Creator: Bond, W. D. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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Conductive Flooring for Hospital Operating Rooms

Description: Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.
Date: March 21, 1960
Creator: Boone, Thomas H.; Hermach, Francis L.; MacArthur, Edgar H. & McAuliff, Rita C.
Partner: UNT Libraries Government Documents Department
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Weapons Effects for Protective Design

Description: A lecture intended to provide a general background in weapons effects is presented. Specific areas of nuclear explosion phenomena pertinent to the design of hardened systems discussed include nuclear radiation and shielding, fireball growth and effects, thermal radiation, air blast, cratering and throwout, ground shock effects, fallout, and afterwinds. (J.R.D.)
Date: March 31, 1960
Creator: Brode, H. L.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for December 1959 and January 1960

Description: The recovery of Th from Blind River ion exchange barrens with di(2- ethylhexyl)phosphoric acid was investigated. The recovery of Tc and Np from fluorination plant residues with tertiary amine was studied. The extraction of Np/sup 4+/ by quaternary ammonium nitrates is reported. A solvent recovery procedure involving successive use of Na/sub 2/CO/sub 3/washing and Al/sub 2/O/ sub 3/- adsorption was demonstrated in laboratory tests as a possible method for the purification and decontamaination of organophosphorus process solvents. The effect of nitrated fractions of Annsco 125-82 on Zr-Nb extractions by TBP was investigated. Treatnnent of TBPAmsco 125-82 solutions with 2 M HNO/sub 3/ at 60 ction prod- C for 1 to 48 hr showed that under these mild conditions the TBP degradation products were more important than those from Amsco as contributors to Zr-Nb extraction and as affecting efficiency of solvent clean-up. The interfacial tensions between benzene solutions of several amine salt and alkyl phosphate extractants and aqueous solutions were examined as functions of the solute concentrations. (For preceding period see CF-59-11-132.) (W.L.H.)
Date: March 1, 1960
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Gresky, A. T. et al.
Partner: UNT Libraries Government Documents Department
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Summary of KER-1 operation, February 15, 1958--March 1, 1960

Description: Recent borescoping of the KER-1 tube revealed several scratches, pits, and gall marks on the internal wall of the tube. These deformations could limit the operating temperature and pressure of KER-1. This report is a summary of operating history and is compiles to assist in determining what contributed to the condition of the tube.
Date: March 3, 1960
Creator: Buckner, C. L.
Partner: UNT Libraries Government Documents Department
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SOME STEADY-STATE THERMAL CHARACTERISTICS OF A THREE-LOOP REACTOR POWER SYSTEM

Description: The three-loop power system which is to be used with Experimental Breeder Reactor No. II (EBR-II) was analyzed to determine the coolant flow rate requirements at various power levels, coolant temperatures at various power levels, effects of heat exchanger sizes (system optimization), and effects of control errors. An intermediate heat exchanger, preheater, evaporator, and superheater are included in the EBR-II power system. Constant thermal resistances and physical properties, and perfect insulation were assumed in the analysis. Among other things, the study showed that at low power levels, excessive thermal stresses are produced at the cold end of the intermediate heat exchanger ualess a high sink temperature is used. It was also found that a short cut may be used to determine approximate system conditions at all power levels, that system optimization requires compromises, and that system flow rate control is possible through high-low measurements of two coolant temperatures in the primary system. (auth)
Date: March 1, 1960
Creator: Bump, T.R. & Monson, H.O.
Partner: UNT Libraries Government Documents Department
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An Improved Nuclear Measuring Principle : Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.
Date: March 28, 1960
Creator: Burgwald, G. M. & Stone, C. A.
Partner: UNT Libraries Government Documents Department
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AN IMPROVED NUCLEAR MEASURING PRINCIPLE. Quarterly Progress Report No. 3 Covering the Period from December 1, 1959 to March 1, 1960

Description: The scintillation counter has proven to be a very valuable research tool, but urfortunately, its ability to meet necessary stability requirements has restricted its use in industrial applications. Several techniques are being investigated which cancel out reasonable variations in detector sensitivity, resulting in improved stability. The general technique consists of alternately measuring the intensity transmitted through the sample and through a calibrated absorber, and difference in intensity causing the calibrated wedge to re-position itself. A comparison of commutating and noncommutating systems is made and other applications of scintillation counter systems are discussed. (For preceding period see ARF-1152-6.) (W.D.M.)
Date: March 28, 1960
Creator: Burgwald, G.M.
Partner: UNT Libraries Government Documents Department
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A LEVEL INDICATOR FOR LIQUEFIED GASES

Description: A capacitance instrument is described that indicates the level of liquefied gas in a closed container. The instrument has been used to indicate and control the level of liquid nitrogen, hydrogen, and methane. (auth)
Date: March 1, 1960
Creator: Burke, A.L. & Cook, L.H. Jr.
Partner: UNT Libraries Government Documents Department
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CHARGE-EXCHANGE SCATTERING OF NEGATIVE PIONS BY HYDROGEN AT 230,260, 290, 317 AND 371 MeV

Description: The differential cross section for charge-exchange scattering of negative pions by hydrogen has been observed at 230, 260, 290, 317, and 371 Mev. The reaction was observed by detecting one gamma ray from the {pi}{sup 0} decay with a scintillation-counter telescope.
Date: March 18, 1960
Creator: Caris, John C
Partner: UNT Libraries Government Documents Department
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