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A Computer Analysis for Complex Sodium Iodide Gamma Spectra
None
Date:
August 1, 1961
Creator:
Mollenauer, J. F.
Object Type:
Report
System:
The UNT Digital Library
REMOTELY CONTROLLED SHEARING OF PIPE AND STRUCTURAL MEMBERS
A shearing tool was developed for remotely controlled severing of pipes or structural members. The shear is rotated about its axis in a wrist motion by the pumped hydraulic fluid that also powers the shear blade. It can be used in a stationary mounting or suspended from a crane. A C-shaped support for the shear was designed to pass through a small top opening of a shielded cell. The controls for manipulating the shear pass through or along the Cframe. The shear jaw opens to 5 in. in height and 7 in. in width, and the total weight of the tool is only 575 lb. It was used to cut metal sections 4 3/4 in. thick and 4-in. sched.-40 stainless steel pipe. (auth)
Date:
December 28, 1961
Creator:
Abbatiello, A. A.
Object Type:
Report
System:
The UNT Digital Library
RADIATION DAMAGE RATES IN NUCLEAR REACTORS. I. THE ELECTRICAL RESISTANCE OF GRAPHITE OVER THE TEMPERATURE RANGE 8-90 C: INITIAL DAMAGE AND ITS TEMPERATURE COEFFICIENT
The behavior of 0.125-in. spectroscopic graphite rods is shown to be variable beyond the variation of measurement. Statistical measures are given for the variability before and with irradiation. The linear regression of the reciprocal per cent change in resistance against the reciprocal exposure was determined from 25 to 90% change of electrical resistance. The linear regression of the above regression coefficients was determined for the range from 8 to 90 deg C. The number of specimens required to achieve a given accuracy in monitoring is calculated. Within the precision of the data, there is no evidence for departure from isothermal damaging, hence no positive evidence of radiation annealing at these temperatures and extents of damage. (auth)
Date:
September 1, 1961
Creator:
Primak, W. & Edwards, E.
Object Type:
Report
System:
The UNT Digital Library
A Process for the Recovery of Uranium From Nuclear Fuel Elements Using Fluid-Bed Drying and Volatility Techniques
A process scheme for the recovery of uranium from fuel elements has been developed. The scheme combines continuous fluid-bed drying and fluoride volatility techniques after initial dissolution of the fuel element in the appropriate aqueous system, hence the designation ADF, Aqueous Dry Fluorination Process. The application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels is described. ln the process, the feed solution is sprayed horizontally through a two-fluid nozzle and is atomized directly in the heated fluidized bed. The spray droplets are dried on the fluidized particles and form a dense coating. Excessive particle growth was limited by the use of air attrition-jets inserted directly in the bed. Aqueous hydrofluoric acid solutions containing l.2 to 3.6 M zirconiuni, 0.007 to 0.03 M uranium, and free acid concentrations from 1 to about l0 M were successfully processed in a 6-in.-diameter Inconel fluid-bed spray dryer. Rates equivalent to about 3.l kg/hr of zirconium were achieved, 160 ml/min with the most concentrated feed solution. Experiments were successfully carried out from 240 to 450 deg C. A new design for a two-fluid nozzle was developed. Extensive work was done to identify the various zirconium fluoride compounds …
Date:
November 1, 1961
Creator:
Levitz, N.; Barghusen, J.; Carls, E. & Jonke, A. A.
Object Type:
Report
System:
The UNT Digital Library
WEATHER MODIFICATION
It is suggested that applying heat directly to a rain cloud, or to a ndoist air mass with rain potential, may alter the natural precipitation in a given geographical region. The immediate effect of the heat is to increase the buoyancy of the cloud or air parcel. The result, which depends on a number of interrelated factors may be either to cause precipitation where it would not naturally occur, or to suppress precipitation where it would naturally occur. Several possible applications are suggested. Since the heat supplied is supplemented by the latent heat resulting from condensation in the moist air mass, the results may more than justify the cost. However, substantial amounts of heat are involved. The heat can be supplied from fossil fuels, nuclear reactions, or a combination of both; but the logistics favor the use of large nuclear reactors wherever safety criteria can be met. Not only the efficiency and economics of the process, but also its feasibility, can be finally decided only on the basis of information that is not now available. (auth)
Date:
December 1, 1961
Creator:
Rodin, M.B. & Hess, D.C.
Object Type:
Report
System:
The UNT Digital Library
The Radiochemistry of Cobalt
The radiochemistry of cobalt is discussed. Included are a review of the nuclear and chemical features of cobalt, a discussion of problems of dissolution of a sample and counting techniques, and a collection of radiochemical procedures for the element as found in the literature. (M.C.G.)
Date:
January 1, 1961
Creator:
Bate, L. C. & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
GAS-COOLED REACTOR PROGRAM. QUARTERLY PROGRESS REPORT FOR PERIOD ENDING JUNE 30, 1961
Activities are discussed for research in design investigations, and materials development and testing conducted in connection with the development of the EGCR. The discussions are given in terms of: reactor physics; reactor design studies; heat transfer and fluid now investigations; materials development; in- pile and out-of-pile testing of components and materials; and development of test loops and components. (B.O.G.)
Date:
August 28, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Processing of Graphite Specimens for High Temperature Irradiation by Hanford
A study was made of the effects of heat treatments to 2900 and 2925 deg C and impregnations on the electric conductivity of HLM-85 and NCC-core graphite specimens. The results are graphed and tabulated. The effects of carbon pickup on the electric conductivty of impregnated samples are shown graphically. (B.O.G.)
Date:
August 1, 1961
Creator:
Engle, G. B.
Object Type:
Report
System:
The UNT Digital Library
POWER-TO-VOID TRANSFER FUNCTIONS
Variations in the distribution of steam bubble, the "void" distribution, in a boiling channel as a function of changes in heating power were studied. A rectangular test tube, of 1.11 x 4.44-cm cross section and 127-cm height, was inserted in a forced-circulation pressure loop. The tube was heated by passing an a-c current through the tube walls. A power oscillator was built which could give a 10% peak-topeak sinusoidal power modulation at any frequency in the interval from 0.01 to 10 cps. Variations in the volume fraction of steam were observed by means of a gamma densitometer built for the purpose. Accurate void profiles could be taken by traversing the test channel vertically and horizontally. With the void detector stationary at a given height, the amplitude and phase delay of the steam void variations were measured in the frequency range mentioned. The signal from the gamma detector was passed to a harmonic analyzer built for the experiment. This instrument could pick out the void variations coherent with the power variation in the presence of much greater random signal variations caused by the boiling process. The frequency response of steam void was measured at 4 different pressures ranging from 27.2 to …
Date:
July 1, 1961
Creator:
Christensen, H.
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
EBR-II Dry Critical Experiments. Experimental Program, Experimental Procedures and Safety Considerations
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.
Object Type:
Report
System:
The UNT Digital Library
A Method of Determining the Intermediate Energy Neutron Dose
The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)
Date:
March 10, 1961
Creator:
Hankins, D. E.
Object Type:
Report
System:
The UNT Digital Library
Arc Melting in the Tungsten Electrode Furnace
An arc furnace is described which employs a nonconsumable tungsten electrode and a water-cooled copper hearth. It is used successfully for melting refractory metals and alloys. The furnace is equipped with a vacuum system, an inert gas supply, and an 800-ampere directcurrent power supply. (auth)
Date:
November 1, 1961
Creator:
Williams, D. E. & Levingston, H. L.
Object Type:
Report
System:
The UNT Digital Library
TITANIUM PUMP LOOP FOR AQUEOUS SOLUTIONS AT HIGH TEMPERATURES
A titanium pump loop, designed to circulate aqueous solutions at temperatures and pressures up to 370 deg C and 3000 psia, was constructed. It is to be used to study the chemical stability of uranyl sulfate fuel solutions of interest to the Fluid Fuels Reactor Program. The total loop voluime was minimized so that about 2 liters uf solution was sufficient for loop operation. The equipment includes a sampling system to remove solution samples from the loop while operating at elevated temperature and pressure; a hydroclone to separate and remove any solids and/or heavyphase material formed; and provisions for installation of corrosion test specimens in the main loop stream. All equipment performed satisfactorily at design conditions in tests with water. (auth)
Date:
December 13, 1961
Creator:
Baker, J.M. & Bolt, S.E.
Object Type:
Report
System:
The UNT Digital Library
REACTOR LABORATORY EXPERIMENTS
An exposition is presented comprising a basic set of experiments in reactor physics, engineering, and technology developed by the International Institute of Nuclear Science and Engineering. Twenty-two experiments are included in a program which may be divided into groups associated with the Argonaut Reactor, the AGN-201 Reactor, and with other reactors or auxiliary equipment. (J.R.D.)
Date:
August 1, 1961
Creator:
Sturm, W.J. ed.
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
Corrosion Tests in Molten Lead-Lead Chloride
Corrosion tests were run on some commercial grade metals, an alloy steel, stainless steels, chromium-- nickel-iron alloys, nickel base alloys, cobalt base alloys, and a chromium-- nickel-- cobalt-- iron ailoy in the system: leadlead chloride-lead chloride vapor at 528 deg C under an argon atmosphere. The following metals and alloys showed a corrosion rate of nine mils per month or less and did not suffer intergranular or other localized attack: tantalum, Incoloy 804, Hastelloy F, Carpenter-20 (Cb), stainless steels 316L, 318 Cb, Haynes Alloy 25, and Haynes Multimet (auth)
Date:
June 1, 1961
Creator:
Stolica, N. D.; Adams, G. S. & Bomar, M. R.
Object Type:
Report
System:
The UNT Digital Library
PL Final Design Report. Supplement
The design of the Army Reactor PL refueling equipment is described. Details of refueling procedures are also given along with a definitive hardware design for the radioactive gas handling equipment which is described in report IDO19030. (J.R.D.)
Date:
January 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
VOID COEFFICIENT OF REACTIVITY ASSOCIATED WITH THE ISLAND REGION OF THE HFIR
Changes in neutron multiplication caused by voids in the island of the HFlR were calculated and measured experimentally. The results indicated that with only water initially in the island the maximum change in neutron multiplication ( DELTA k/sub max) associated with island voids is 0.032 with a corresponding void fraction of 70%. With a simulated 300 g Pu target in the island DELTA k/sub max/ was 0.0l6, and the corresponding void fraction was 42%. In view of these large changes in neutron multiplication, calculations were made to determine what additional materials could be used in the island to reduce DELTA k/sub max/ and what the associated decrease in peak thermal flux wouId be. The results indicated that of the materials considered the use of beryllium in the water island resulted in the smallest decrease in flux for a specified DELTA k/sub max/. To reduce DELTA k/sub max/ to 0.01 required 26% by volume of beryllium in the island; the corresponding reduction in thermal flux, as compared to an all-water island, was about 10%. In order to reduce DELTA k/sub max/ to 0.0l with a 300 g Pu target in the island, the aIuminum-to-water ratio of the target had to be …
Date:
November 15, 1961
Creator:
Cheverton, R.D.
Object Type:
Report
System:
The UNT Digital Library
STEAM-COOLED POWER REACTOR EVALUATION, STEAM-COOLED FAST BREEDER REACTOR
Conceptual design and economic studies of a steamcooled fast breeder reactor that can also be used as a source of power are presented. Two reactor plant sizes were considered: a 300-Mw(e) central power station plant and a 40 Mw(e) plant. It was concluded that attractive economics and good breeding characteristics breeding ratios from 1.27 to 1.42) can be achieved in steam- cooled PuO/sub 2/UO/sub 2/ fueled fast reactors. Low capital costs can be obtained by a compact reactor core and the absence of large heat exchangers and complicated process systems. Reactor design data are discussed. Analysis showed that these reactors can be prevented from going prompt critical, when fully flooded, by incorporating a tolerable amount of high resonance absorption materials such as hafnium or indium. An increase in reactivity on loss of coolant was indicated by preliminary calculations. (M.C.G.)
Date:
April 15, 1961
Creator:
Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Object Type:
Report
System:
The UNT Digital Library
GEOMETRICAL CONSIDERATIONS IN THE MEASUREMENT OF THE RATIO L/R IN THE SCATTERING OF POLARIZED NUCLEONS
A FORTRAN II program is described which is used to evaluate the effect of a spatially extended analyzer and detector on the measurement of the left- right asymmetry in the scattering of polarized particles. The initial scatterer is assumed to be a point source and the analyzer, second scatterer, and detector are treated as planes whose dimensions are adjustable as input data in the program. The calculation allows for any glven angular distribution of particle flux from the source if this distribution can be represented as a finite power series in the cosine of the angle of emission. A similar representation is used to describe the scattering properties of the analyzer. The integrals over the finite dimensions of the analyzer and detector are evaluated by a standard Newton- Cotes quadrature approximation for multidimensional integration. A discussion of this approximation as well as a listing of the FORTRAN program are included. (auth)
Date:
September 1, 1961
Creator:
Monahan, J.E. & Elwyn, A.J.
Object Type:
Report
System:
The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART I. ZIRCONIUM IN HCl- METHANOL
The electrolytic dissolution of zirconium in HCl-methanol was studied as a function of potential, solution composition, and temperature. The dissolution is characterized by two regions. At high potentials the zirconium is electropolished and complete dissolution is achieved. At low potentials the current is an exponential function of the potential (Tafel behavior). In this region a small amount of finely divided alpha -zirconium which is insoluble in HCl-methanol separates from the bulk metal. The energy of activation for the corrosion reaction (0.0 volt) is 16.5 kcal/mole; in the electropolishing region (1.0 volt) the activation energy is 7.7 kcal/mole. A broad solvent capability for metallic reactor fuels is offered by the HCl-methanol medium since, in addition to zirconium, stainless steel is also dissolved electrolytically while uranium and aluminum dissolve chemically. Other process implications are discussed. (auth)
Date:
December 29, 1961
Creator:
Aylward, J. R.; Whitener, E. M. & Hahn, H. T.
Object Type:
Report
System:
The UNT Digital Library
Isotopic Sources of Secondary Radiation. Final Report
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.
Object Type:
Report
System:
The UNT Digital Library
THEORETICAL STUDY OF OPTICAL PROPERTIES. PHOTON ABSORPTION COEFFICIENTS, OPACITIES, AND EQUATIONS OF STATE OF LIGHT ELEMENTS INCLUDING THE EFFECT OF LINES. Final Report. APPENDIX A: THERMODYNAMIC PROPERTIES AND MEAN OPACITIES
Photon absorption coefficients and mean opacities were calculated for hydrogen, beryllium, carbon, nitrogen, aluminum, and silicon over a temperature range froni l.5 to 34 ev and a density range from about l0/sup -1/g/cm/sup 3/ downward. Contributions to the absorption coefficient from free-free (inverse- bremsstrahlung), bound-free (photoelectric), and bound-bound (line-absorption) processes are included, as is Compton scattering. Certain thermodynamic properties are also given. An improved recipe for pressure ionization was derived which is approximately valid at nondegencrate densities for any ratio of Debye length to ion-sphere radius. Line absorption was evaluated using recent results from pressure-broadening theory and a representation of line series which is computationally as simple as the statistical method. The results show that lines increase the Rosseland mean opacity by a factor which can be nearly ten and which is insensitive to moderate changes in line widths. The code employed generated ionic energy levels internally by isoelectronic interpolation, and is immediately applicable to any- mixture of elements in which no ion has more than 14 bound electrons. The results of the calculations of thermodynamic properties and mean opacities are given in the tables in Appendix A, and the graphs of the monochromatic absorption coefficients are given in Appendix …
Date:
September 1, 1961
Creator:
Stewart, J.C. & Pyatt, K.D. Jr.
Object Type:
Report
System:
The UNT Digital Library