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Recording Equipment for Internal Friction Measurements
An apparatus was developed for recording internal friction data in such a manner as to circumvent many of the laborious and time-consuming observations and calculations usually associated with these measurements. An optical lever is used and the passage of the beam across the scale is detected by photoconductive cells. The cells are strategically located so that, when their signals are fed through a multichannel switching circuit to the pens of an operation recorder, a plot of the logarithm of the vibrational amplitude versus the number of cycles is recorded on the chart. From the definitmon of the logarithmic decrement, ( delta ), it can be shown that the slope of this curve is - delta . The apparatus is inexpensive and requires a minimum of maintenance. It has been used for accurate determinations of values of delta from below 0.0001 up to 0.3. (auth)
Date:
October 31, 1961
Creator:
Stephenson, R. L. & McCoy, H. E. Jr.
Object Type:
Report
System:
The UNT Digital Library
Diffusion of Slow Electrons in Gases
The properties of electrons in a gas and an external electric field, e.g., agitation velocity, free path, energy lost per collision, and collision cross sections, were determined for electrons of energy less than 2 ev in a large number of gases. The computations were made from previously measured values for Townsend's energy factor or the ratio of electron agitation energy to molecule thermal energy. Results are presented for hydrogen, nitrogen, carbon dioxide, methane, ethylene, cyclopropane, and argon. (D.L.C.)
Date:
October 24, 1961
Creator:
Forester, D. W. & Cochran, L. W.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
THE CALCINATION IN AIR OF BERYLLIUM OXALATE TRIHYDRATE TO BERYLLIUM OXIDE
None
Date:
October 19, 1961
Creator:
Hamner, R.L. & Harris, L.A.
Object Type:
Report
System:
The UNT Digital Library
Waste Treatment and Disposal Progress Report for June and July 1961
7 7 6 4 : 9 8 9 6 5 : 9 aluminum nitrate waste was calcined in the close-coupled continuous evaporator-pot calciner unit. Waste oxides from TBP-25 waste were incorporated into glassy materials after the addition of phosphate and borate fluxing agents. Melts formed at 850 to 950 deg C were glassy solids when cooled and had densities from 2.41 to 2.47 g/ml. Waste volurne reduction factors were from 7.6 to 9.3. Low-Level Waste Treatment. A demonstration run was completed in the 60 liters/hr scavenging-ion exchange pilot plant on ORNL low-activity waste. Decontamination factors were satisfactory after 1500 resin bed voluumes of waste had been treated, i. e, Sr> 1000, TRE 100, Cs> 100, and sufficiently high for other activities that the waste activity was reduced to <10% of MPC. The physical properties of vermiculite, clinoptilolite, and rock phosphate were found to be suitable for second-stage treatment of process waste. Engineering, Econommc, and Hazards Evaluation. A cost study of the conversion of high-level solutions to solids by pot calcimation was completed. Aging had a negligible effect on costs for processing in a given vessel size. The lowest cost was 0.87 x 10/sup-2/ mill/kwh/sub 3/ for processing acidic Purex and …
Date:
October 24, 1961
Creator:
Blanco, R. E. & Struxness, E. G.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the University of New Mexico Conference on Organic Scintillation Detectors, August 15-17, 1960
Twenty-three papers are included which were presented at the Conference on Organic Scintillation Detectors. The topics treated range from measurements of organic phosphor properties to liquid and plastic scintillation detectors. Separate abstracts were prepared for each of the papers. (D.L.C.)
Date:
October 31, 1961
Creator:
Daub, G. H.; Hayes, F. N. & Sullivan, E.
Object Type:
Report
System:
The UNT Digital Library
STUDIES IN MICROMERITICS. II. THE DEPOSITION OF PARTICLES IN CIRCULAR CONDUITS DUE TO THERMAL GRADIENTS
The deposition of particles from turbulent gas streams due to thermal gradients was predicted using a simplified flow medel. In the medels particle concentration was assumed constant in the turbulent region. The particle deposition velocity was taken to be the radial velocity of thermal - repulsion in the laminar sublayer. Temperature gradients in the laminar sublayer were calculated for constant wall temperature using the Reynoldss analogy. The loss magnilude of suspended particles from loss due to thermal deposition is not generally greats and is most important for submicron particles. (auth)
Date:
October 1, 1961
Creator:
Postma, A.K.
Object Type:
Report
System:
The UNT Digital Library
Electrolytic Dissolution of Power Reactor Fuels in Nitric Acid
The electrolytic oxidation in nitric acid of stainless steel, zirconium, Zircaloy-2, zirconium- uranium alloy, aluminum, and uranium - molybdenum alloy was demonstrated on a laboratory scale. The rate of chemical dissolution of UO/ sub 2/ in nitric acid was measured. Corrosion of stainless steel by these dissolver solutions was measured and found to be negligible. Electrolytic dissolution was demonstrated to be a practical technique for the first step in processing fuel elements of several types of power reactors. (auth)
Date:
October 1, 1961
Creator:
Clark, A. T., Jr.; Meyer, L. H.; Owen, J. H. & Rust, F. G.
Object Type:
Report
System:
The UNT Digital Library
THE RELEASE OF Kr$sup 85$ FROM UO$sub 2$ IN ORR CAPSULES
In an attempt to determine the validity of the method of predicting the release of fission gases from U0/sub 2/ suggested recently by Cottrell et al., a series of calculations were made of the expected release of Kr/sup 85/ from prototype Experimental Gas-Cooled Reactor (EGCR) fuel capsule irradiated in the Oak Ridge Research Reactor (ORR). The computed values were then compared with measured values of the per cent Kr/sup 85/ released. In the calculations, the thermal conductivity of the U0/sub 2/ was assumed to be 0.028 w/cm- deg C in the temperature range from 700 to 1600 deg C, and in the absence of a precise knowledge of the helium gap, the cases of a 3-mil helium gas and no gap were treated. Values of the release-rate parameter (D) were estimated from BET surface areas of the U0/sub 2/ pellets. Results showed that the measured values of the per cent Kr/sup 85/ released generally fell within or close to the limits set by the 3-mil helium gap and no gap conditions. There was also a definite correlation between the measured values and the 3-mil gap condition when the clad temperature was about 700 deg C. When the clad temperature was …
Date:
October 1, 1961
Creator:
Scott, J.L.
Object Type:
Report
System:
The UNT Digital Library
HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report
The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employing the above analytical model. No advantage in retarding combustion was found in using silicon carbide coated fuel sleeves. The negative results of these tests are due both to the particular geometry of the EGCR moderator and sleeves as well as to the fact that all sleeves tested contained imperfections in the coatings. Chlorine was demonstrated to be an effective agent for extinguishing graphite fires. Concentrations in air of about 1% were observed to extinguish graphite fires at temperatures as high as 1000 deg C. (auth)
Date:
October 10, 1961
Creator:
de Halas, D.R.; Dahl, R.E. & Jackson, J.L.
Object Type:
Report
System:
The UNT Digital Library
In Vivo Gamma Lung Measurements--a Mathematical Model
A low-background facility is described for rneasuring lung burdens of U, Th, and other nuclides in vivo. Problems associated with this method of radiation measurement are discussed. A mathennatical, computer-oriented simulation was devised to gain insight into the relation of the net observed radiation spectrum to the burden of radioactivity in the body or its organs. Chest cavities for persons of three sizes were synthesized in a three-coordinate space comprised of one-inch cubes and including a 9-in.-diameter crystal detector. Data, describing the tissue composition of each cube in the body and the characteristic radiation attenuation for each tissue-type, were coded for use with a program on a high-speed digital computer. Efficiencies for measuring radiation emitted by numerous point sources of enriched uranium were calculated. Data on in vivo measurement efficiency were obtained assuming uniform distribution of radioactive material throughout the lungs and also for nonuniform deposits. The effects of individual size and geometry, and of detector position on the measurement efficiency were determined for these twvo categories and radiation flux distributions on the detector face were computed in some cases. Data are appended and a flow diagram of the computer program is included. (C.H.)
Date:
October 20, 1961
Creator:
Ammann, P. R.; Wilson, C. W. & Mohr, C. M.
Object Type:
Report
System:
The UNT Digital Library
Analytical Chemistry of the Polyphosphates
Additional data were obtained on the separation of linear polymers from cyclic polymers by precipitation with barium chloride. An unexpected peak was observed in the anion-exchange chromatography of a sodium poly-phosphate of n-bar average degree of polymerization) = 6, and the compound represented by this peak was isolated. An end-group titration of this compound by microtechnique proved unequivocally that it is a cyclic phosphate. Although the identification (number of phosphorus atoms per molecule) is not completed, evidence from its position in the elution graph by ion-exchange chromatography' and from paper chromatography indicate that it is probable pentametaphosphate, Na/sub 5/P/sub 5/O/sub 15/, or the boat form of tetrametaphosphate, Na/sub 4/P/sub 4/O/sub 12/. (P.C.H.)
Date:
October 17, 1961
Creator:
Rieman, W., III & Rothbart, H. L.
Object Type:
Report
System:
The UNT Digital Library
EXTRACTION OF NEPTUNIUM FROM ACIDIC SOLUTIONS BY ORGANIC NITROGEN AND PHOSPHORUS COMPOUNDS
Neptunium distribution coefficients from acid nitrate, chloride, and sulfate solutions by several organic nitiogen and phosphorus compounds were measured as functions of several extraction variables, including neptunium valence, acid and salt concentration, and reagent concentration. Extractability by all the reagents varied in the order Np(IV)> Np(VI)>> Np(V). Except for primary amines, all reagents extracted Np(IV) much more strongly from nitrate than sulfate solutions. Among organonitrogen compounds the order of extractability of Np(IV) was: quaternary> tertiary> primary and secondary from nitrate solutions but primary>> secondary> tertiary from sulfate solutions. Neptunium(IV) nitrate extractions with the different extractants passed through maxima at widely different acid concentrations. In most cases, extraction increased when nitric acid was replaced by nitrate salt. Extraction was usually approximately proportional to the square of the reagent concentration. (auth)
Date:
October 19, 1961
Creator:
Weaver, B.
Object Type:
Report
System:
The UNT Digital Library
Hazards Report for the BF3 Withdrawal Mechanism in the SM-1
A design and operational description is presented of a BF/sub 3/ withdrawal mechanism planned for installation on one of the two startup channels at the SM-1. An analysis of possible malfunctions is included. (J.R.D.)
Date:
October 13, 1961
Creator:
Coombe, J. R.
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS QUARTERLY PROGRESS REPORT. SECTION I. USE OF INTRINSIC RADIOACTIVE TRACERS FOR PROCESS CONTROL. SECTION II. RADIATION-INDUCED GRAFT-POLYMERIZATION STUDIES
Research was continued in the areas of intrinsic radioactive tracers for industrial process control and the influence of structural factors in radiation- induced graft polymerization. The use of in-process isotope neutron soarces to produce short-lived radiotraces is discussed. A 10c Po--Be neutron source was obtained for exploratory experiments. The design and construction of a neutronsource storage shield and an activatioa-cell holder are underway. The effect of structural factors oii the eIficiency of free-radical site formation in acrylate and methacrylate polymers was emphasized. Site measurements versus dose were made for poly-n-hexylmethacrylate. Two additional methods for measuring free-radical conceiitrations, a chemical method employing diphenylpicrylhydrazyl and hydroquinone and a method based on molecular-weight decreases, were developed. The grafting studies were continued. (M.C.G.)
Date:
October 23, 1961
Creator:
McFarling, J.L.; Gluck, P.; Kircher, J.F.; Sunderman, D.N.; Sliemers, F.A.; Luttinger, M. et al.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for Period April 1 through June 30, 1961
BS>Activities are discussed for work done in the preparation of PuO/sub 2/ using the continuous oxalate process, and continuous coprecipitation studies using a uranium-20 wt% plutonium nitrate feed solution. Characterization studies of the PuO/sub 2/ powders indicated that variations in the processing variables can affect the final product. Measurements with the B. E. T. and Innes apparatus confirmed that the specific surface area of the initial batch of the PuO/sub 2/ powder had increased appreciably during storage. Deltatherm differential thermal analysis apparatus was checked out. Procedures were devised for the determination of plutonium and uranium. Sintering studies were continued for pure PuO/sub 2/, and sintering trials were begun for mechanically mixed and coprecipitated PuO/sub 2/ and UO/sub 2/. Metallographic examinations of PuO/sub 2/ sintered pellets revealed a microstructural feature similar to eutectoid structures in alloys. Mechanical packing experiments were carried out using crushed UO/sub 2/ pellets fired to high density. Plasma torch production of UO/ sub 2/ indicates that excellent spheroidization is attained, but central voids were found in the pellets. Reactor physics studies were completed for the analysis of the potential of plutonium as a fuel in near-thermal converter and straight burner reactors. Plutonium was shown to be promising …
Date:
October 31, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
THE EFFECTS OF INTERNAL HEAT GENERATION ON POT CALCINATION RATES FOR RADIOACTIVE WASTES
Methods by which the radial deposition mechanism was determined in experiments with simulated waste solutions are reviewed. Based on this mechanism, an expression for the rate of solid deposition with internal heat generation was developed by a combined heat and material balance. A sample calculation for Purex waste showed that a moderate heat generation rate of 5000 Btu/hr/ft/sup 3/ would decrease the time to fill a 12-in.-dia calcination vessel from 78 to 55 hr. For the calcination stage of the process in which the deposited solids are heated in the absence of a liquid phase, a solution was developed for the equation of heat transfer with the temperature profile from the solid deposition stage as an initial condition. For the example Purex waste with a heat generation rate of 5000 Btu/hr ft/sup 3/, less than 15 min would be required for calcination, compared to about 8 hr in experiments with simulated wastes. (auth)
Date:
October 23, 1961
Creator:
Perona, J.J.
Object Type:
Report
System:
The UNT Digital Library
A Simulation of the EGCR Steam Generator
An analog model of the EGCR steam generator was developed and operated on the ORNL analog computer as part of a program to simulate the operation and control of the EGCR reactor plant. Equilibrium operation and the transient response of the steam generator unit to system perturbations were studied. A simultaneous solution of the basic heat transfer equations representing the performance of the unit was obtained. The model was operated initially at steady- state conditions, and then perturbations were made to gas flow, gas inlet temperature, and steam throttle valve position. The response characteristics of the model during the transients were recorded. The steam generator gas outlet temperature showed a marked degree of insensitivity to changes in gas inlet temperature. The effect of gas flow changes on gas exit temperature was slightly more pronounced. The transient behavio-r of the unit was reasonable, and the model developed indicated satisfactory operation within the design range of 20 to l00% of full power. (auth)
Date:
October 1, 1961
Creator:
Yarosh, M.M. & Ball, S.J.
Object Type:
Report
System:
The UNT Digital Library
Economic Analysis of Replacement Cores for SM and PM Type Reactors
An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies. The analysis indicates that major savings are possible by utilizing Type 3 cores (40-mil plates, 25 wt% UO/sub 2/, welded assembly) in all SM and PM type reactors, and that significant savings are possible by multiple core procurement and reprocessing, and relaxation of cobalt and tantalum requirements in Type 347 stainless steel. (auth)
Date:
October 1, 1961
Creator:
Wilder, A. S.
Object Type:
Report
System:
The UNT Digital Library
Sodium Iodide and Sodium Iodide Crystals: Their Use in Scintillation Counting and Spectrometry. A Bibliography
References (297) were obtained from Applied Science and Technology Index, Chemical Abstracts, Dissertations in Physics, Nuclear Science Abstracts, and Science Abstracts, Section A. The period covered was from 1948 through l960. The arrangement is alphabetical by title; personal author and subject indexes are included. (P.C.H.)
Date:
October 1, 1961
Creator:
Kepple, R.R.
Object Type:
Report
System:
The UNT Digital Library
RESEARCH ON THE EFFECTS OF MAGNETIC FIELDS ON THERMIONIC POWER GENERATION. Progress Report No. 1
Research concerned with a theoretical and experimental study of magneto- thermionic power generation is reported. This concept promises a number of advantsges over conventional thermionic generators. Low pressure Cs diodes suffer from an undesirable size limitation, because selfinduced magnetic fields reduce current transmission and hence, efficiency. Although this effect does not arise in the small devices tested to date, it becomes important in building larger generators. Analysis indicates that this problem can be virtually eliminnted by the application of a longitudinal magnetic field. An experimental and theoretical study was initiated to verify the predicted magnetic field effects, and to examine their possible use in a-c generation. (auth)
Date:
October 1, 1961
Creator:
Schock, A. & Kunen, A.E.
Object Type:
Report
System:
The UNT Digital Library
RADIOACTIVITY OF NUCLEAR REACTOR COOLING FLUIDS
Methods were developed for analysis of cooling water for impurities, radioisotopes, etc., and experimental results are presented for the ORNL Research Reactor. The theory of nuclear reactions in a water-cooled reactor is discussed at length, and equations were developed which allows predictions of equilibrium conditions from nonequilibrium measurements. The equations were verified experimentally by work on the ORNL Research Reactor and can be extended to other reactors. The origins of Na/sup 24/, Cd, and fission product activities are discussed, and the possibility of fuel element rupture detection by delayed neutron measurements is considered. (D.L.C.)
Date:
October 1, 1961
Creator:
Ward, J.C.
Object Type:
Report
System:
The UNT Digital Library
An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters
Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 7l atm (l050 psia) or l67 atm (2450 psia). A preliminary screening of ten different reactor concepts resulted in the selection of two for a detailed evaluation. These are a direct-cycle, watermoderated reactor, and an indirect-cycle, sodium-cooled reactor. The steam- cooled, water-moderated system is judged to have the best chance for initially reaching 566 deg C (l050 deg F), whereas, the indirect-cycle, sodiumcooled system is considered best for subsequent advances to exploit the more efficient, high- pressure steam reheat cycles. A design concept was selected for each of the reactors to establish a basis for the detailed evaluations and comparisons. The technical evaluation of the two concepts shows that the sodium-cooled, indirect- cycle superheater can realize a significant reductlon in the gross plant heat rate STA0.6097 to 0.5404cal/watt-sec (87l0 to 7720 Btu/kwh)! by use …
Date:
October 1, 1961
Creator:
Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Object Type:
Report
System:
The UNT Digital Library
THE CYCLOTRON RESONANCE INSTABILITY WITH NEGATIVE MASS IONS
Both the effect of resonant coupling of ion cyclotron motion to electron plasma oscillations, as previously discussed by Harris, and the effect of a negative radial gradient in a magnetic mirror field, the so-called "negative mass'' effect, were combined in an approximate calculation for the threshold for electrostatic instability in DCX. The two mechanisms for instability were found to act more or less independently. (auth)
Date:
October 17, 1961
Creator:
Fowler, T.K. & Harris, E.G.
Object Type:
Report
System:
The UNT Digital Library
TERMINAL REPORT ON THE BOILING SLURRY REACTOR EXPERIMENT (SLURREX). (Mockup Hydraulic Experiments)
None
Date:
October 1, 1961
Creator:
Lokay, J. D.
Object Type:
Report
System:
The UNT Digital Library