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ANHARMONIC POTENTIAL CONSTANTS AND THEIR DEPENDENCE UPON BOND LENGTH
Empirical study of cubic and quartic vibrational force constants for diatomic molecules shows them to be approximately exponential functions of internuclear distance. A family of curves is obtained, determined by the location of the bonded atoms in rows of the periodic table. Displacements between successive curves correspond closely to those in Badger's rule for quadratic force constants (for which the parameters are redetermined to accord with all data now available). Constants for excited electronic and ionic states appear on practically the same curves as those for the ground states. Predictions based on the diatomic correlations agree with the available cubic constants for bond stretching in polyatomic molecules, regardless of the type of bonding involved. Implications of these regularities are discussed. (auth)
Date:
August 1, 1961
Creator:
Herschbach, D.R. & Laurie, V.W.
Object Type:
Article
System:
The UNT Digital Library
Status Report on the Argonne Advanced Research Reactor
The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and construction, plant ventilation, heating and air conditioning, critical experiments, reactor physics, heat transfer studies, and shieldings are discussed. (M.C.G.)
Date:
November 1, 1961
Creator:
Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Object Type:
Report
System:
The UNT Digital Library
HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20
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.
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS
Procedures for assembling EBR-II fuel elements with annular sodium bonds between the uranium rods and the stainless steel claddings are outlined. The results of several meltdown and uranium-settling experiments are given. Bonding experiments were performed: furnace bonding, submerged canning, ultrasonic bonding, centrifuging, pressure pulsing, and vibratory bonding. Vibratory bonding was chosen for the production of the first EBR-II core. (D.L.C.)
Date:
July 1, 1961
Creator:
Sowa, E.S. & Kimont, E.L.
Object Type:
Report
System:
The UNT Digital Library
Organic Nuclear Reactors: An Evaluation of Current Development Programs
Organic reactor technology is critically evaluated and areas of research and development work now lacking or inadequate for the successful development of this reactor concept are indicated. The development programs for present organic and heavy water moderated concepts appear generally adequate to reach specific goals. However, the narrow scope of the organic reactor program should be broadened to assure coverage of areas where the application of novel principles might result in marked economic benefits. Further work, principally of a basic nature, is recommended in the fields of chemistry, processing, management, and thermodynamic properties of coolants, in fuel development, and in concept evaluation. (N.W.R.)
Date:
May 1, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Oscillating Vertical Magnetic Dipole Above a Conducting Half-Space
The electromagnetic field produced by a vertical oscillating magnetic dipole above a plane conducting earth is obtained in integral form. An exact solution in closed form is obtained for the case in which the dipole and the point of observation are both located on the surface of the earth. (auth)
Date:
April 1, 1961
Creator:
Wesley, J. P.
Object Type:
Report
System:
The UNT Digital Library
Cost Function Studies for Power Reactors
A function to evaluate the cost of electricity produced by a nuclear power reactor was developed. The basic equation, revenue = capital charges + profit + operating expenses, was expanded in terms of various cost parameters to enable analysis of multiregion nuclear reactors with uranium and/or plutonium for fuel. A corresponding IBM 704 computer program, which will compute either the price of electricity or the value of plutonium, is presented in detail. (auth)
Date:
November 1, 1961
Creator:
Heestand, J. & Wos, L.T.
Object Type:
Report
System:
The UNT Digital Library
REACTOR MAIN COOLANT LOOP
A parametric study was made for the POPR with temperature gradients of 610 to 670 deg F and 6l0 to 684.5 deg F at organic flow rates of 17.8 x l0/sup 6/ and l4.4 x l0/sup 6/ lbs/hr, respectively; and steam turbine conditions at the throttle of 600 and 650 deg F at 800 to l200 psig. The study was made to obtain the most economical layout of the main heat transfer loop system. (B.O.G.)
Date:
August 1, 1961
Creator:
Terpe, G.R. & Katz, B.
Object Type:
Report
System:
The UNT Digital Library
Off-Site Radiological Safety Report, Carlsbad, New Mexico
A summary ls presented of the off-slte radiological safety actlvities of the U. S. Public Health Service during the Project Gnome operation. Topics dlscussed include: operational procedures; collection of data by aerial monltoring, mobile monitoring, potash mlne surveys, air sampling, milk sampllng, water sampling, soil and vegetation sampllng, and a film badge program; laboratory control, emergency measures; medlcal services; and veterinary activltles. It was concluded that no persons ln the vlclnlty of the Gnome test site recelved harmful amounts of radlation either lnternally or externally. (M.C.G.)
Date:
January 1, 1961
Creator:
Placak, O. R.
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
Biological Effects of Blast. Technical Progress Report
The current state of knowledge relevant to biological blast effects was summarized in a selective manner. Initially, five problems of concern to those who would relate the environmental variations produced by nuclear weapons with biological response and hazard assessment were pointed out. Primary, secondary, tertiary, and miscellaneous blast effects were defined and selected interspecies experimental data of a physical and pathophysiological nature useful in estimating human response were presented. Tentative biological criteria defining safe levels of exposure were set forth as were survival curves for different conditions of exposure in Hiroshima. These were discussed along with the comparative variations in range of the free-field effects as they vary with explosive yield. The fundamental requirement for surviving seconds, minutes, and hours to abet survival for days, weeks, months, and years was emphasized along with the necessity for planning protective measures against all hazardous weapons effects as one attractive alternative for minimizing casualties and maximizing survival in the event of a nuclear war. (auth)
Date:
December 1, 1961
Creator:
White, C. S.
Object Type:
Report
System:
The UNT Digital Library
Response of Dual-Purpose Reinforced-Concrete Mass Shelter
BS>A reinforced-concrete dual-purpose underground parking garage and personnel sheiter designed for a long-duration incident pressure of 40 psi was tested. The sheiter was exposed to shot Priscilla, an approximately 37-kt 700-ft balloon burst (June 24, 1957), at a ground range of 1600 ft (predicted 35-psi peak incident-pressure level). The recorded peak incident pressure at the shelter was approximately 39 psi. Postshot soil borings were made to obtain undisturbed samples for determining soil characteristics. Preshot and postshot field surveys were made to determine the total lateral and vertical displacement of the structure. The test structure provided adequate protection from the effects of the test device at the test GZ distance. Despite failure of the door sealing gasket, a rise in pressure in the interior did not exceed 1.0 psi. The flat-slab roof and supporting structure were more than adequate to resist the 39psi peak incident test loading. (P.C.H.)
Date:
April 1, 1961
Creator:
Cohen, E.; Laing, E. & Bottenhofer, A.
Object Type:
Report
System:
The UNT Digital Library
CRITICAL EXPERIMENTS FOR THE PRELIMINARY DESIGN OF THE ARGONNE HIGH FLUX REACTOR
Critical experiments were performed with two assemblies simulating a cold clean, and an end-of-cycle,- Argonne High Flux Reactor, core. Data were obtained for flux distributions; cadmium ratios; temperature and void coefficients; and control rod, beam hole, and reflector worths. The data obtained furnished confirmation of theoretical predictions. The peak 2200-m/sec flux per unit power was measured as 3 x 10/sup 7/ n/(cm/sup 2/)(sec)(watt) for both cores. The two cores had internal H/sub 2/O thermal columns, 12.7 cm x 12.7 cm x 50.8 cm. These were enclosed by 100-liter fuel zones. The radial reflector was 90% beryllium containing 10% H/sub 2/0 plus Plexiglas by volume. The top and bottom reflectors were H/sub 2/O. The critical mass was 3.58 kg U/sup 235/ with a 1.16 metal-towater ratio in the fuel zone. The critical mass with a 1.60 metal- to-water ratio, taking into account 34.3 kg Type 304 stainless steel, was 7.15 kg U/sup 235/. (auth)
Date:
June 1, 1961
Creator:
de Villiers, J.W.L. ed.
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
Adsorption of Krypton and Xenon by Various Materials
The adsorptive capacities of various inorganic adsorbents and activated charcoals for krypton and xenon were determined. Columbia-G activated charcoal had the highest capacity for both krypton and xenon at pressures from 0.01 to 125 mm Hg and temperaturens from 2 to 85 deg C. If a value of 1 is assigned to the capacity of this charcoal at 28 deg C for krypton, other charcoals range from 0.63 to 0.84, molecular sieves (except 4A) from 0.11 to 0.20, and some silica genls from 0.05 to 0.07. Various othenr adsorbennts, including one variety of silica gel and molecular sieve 4A, range from 0.005 to 0.032. Molecular sienve 5A and Columbia-G charcoal adsorbed 11.5 times more xenon than krypton. Adsorption of 7.5% water by either of these adsorbents lowerend their capacity for krypton 25 to 30%, while saturating the sieve material ( approximates 15% H2O) lowered the krypton capacity 80%. (auth)
Date:
December 1, 1961
Creator:
Lloyd, M. H. & McNees, R. A.
Object Type:
Report
System:
The UNT Digital Library
A THEORETICAL STUDY OF SIMPLE MANY-ELECTRON SYSTEMS
None
Date:
May 1, 1961
Creator:
Sachs, L.M.
Object Type:
Report
System:
The UNT Digital Library
Transient Temperature Distributions in a Thermally Orthotropic Plate With Non-Uniform Surface Heating
ent temperature variation in a thermally orthotropic plate which is subjected to an arbitrary heating rate distribution along one face with all other surfaces being insulated. Dimensionless temperature histories and distributions determined from this solution are presented for the special, but representative, case of a linearly varying heating rate distribution on plates with varying degrees of thermal orthotropy. These results establish quantitatively the value of a material with high planar and low normal thermal conductivities for applications where it is desired to maintain minimum temperatures on the rear or unheated surface of a heat shield when the heated surface is subjected to a very non-uniform heating rate distribution. The applicability of simplifying assumptions in analyzing such a system is discussed. Experimental temperature measurements in a pyrolytic graphite plate heated by an oxyacetylene flame were made to verify the analytical results. Achievement of satisfactory agreement wss found to be dependent upon use of thermal property values differing from those presently available for this material. This is not unusual in that differences in production methods are known to introduce substantial property variations in anisotropic materials such as pyrolytic graphite. (auth)
Date:
June 1, 1961
Creator:
Hornbaker, David Ross
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
SNAP 2 REACTOR PUMP DEVELOPMENT PROGRAM (RADIAL GAP PERMANENT-MAGNET PUMP)
A compact electromagnetic pump utilizing a rotating permanent magnet with radial gap was developed for possible application to the SNAP 2 reactor coolant system. The pump was designed for circulation of NaK at 1000 deg F and 11.2 gpm with a developed pressure of 3 psi, operation at 40,000 rpm, minimum weight and size, and high reliability. The performance characteristics of four developmental pump models were measured in a 1000 deg F NaK test loop and compared with design predictions. The capability of the pump design concept was demonstrated, though further development work is needed to meet the SNAP 2 pump requirements. A flow capacity of 6.8 gpm of NaK at 1000 deg F with a developed head of 3 psi with attained at a magnet rotor speed of 40,000 rpm. The weight of this pump is 3 pounds. Reasonable agreement was obtained between the actual pump characteristics and the design predictions. (auth)
Date:
September 1, 1961
Creator:
Sudar, S.
Object Type:
Report
System:
The UNT Digital Library
Seal-Shell-a Digital Program to Determine Stresses and Deflections in an Axisymmetric Shell of Revolution
SEAL-SRELL, a FORTRAN II program registered as code number M0077 at Bettis Atomic Power Laboratory, is written for the Philco 2000 computer with two tape units. The program is designed to determine loads, deflections, and stresses in a thin shell of revolution under axisymmetric end loads and pressure. (auth)
Date:
September 1, 1961
Creator:
Friedrich, C.M.
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
Annotated Bibliography of Theories of the Equation of State of Ionized Gases and Strong Electrolyte Solutions
This bibliography lists 297 references on the equation of state of ionized gases and electrolyte solutions, including calculations of closely related quantities such as free energy, partition functions, o smotic pre ssure, activity coefficients, and equilibrium compositions of partially ionized systems. A subject index and a supplementary list of 42 bibliographies on plasma physics and similar topics are included. (auth)
Date:
August 1, 1961
Creator:
Brush, S. G. & Wensrich, C. J.
Object Type:
Report
System:
The UNT Digital Library
SPERT IV HAZARDS SUMMARY REPORT
Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this facility is considered to be a severe nuclear excursion which results in the destruction of the reactor building and the release of 100% of the accumulated fission product inventory of the atmosphere in a steam cloud. The fission product source assumed in the analysis of this accident is an upper limit in view of the nature of the tests to be performed and the heat removal capacity of the system. This postulated accident is independent of the details of core and control system design and is valid for all cores anticipated for use in the experimental program. The major hazards present in the operation of this facility, the precautions to be taken to reduce the probability of an accident, and the consequences of the maximum possible …
Date:
July 1, 1961
Creator:
Bentzen, F. L. & Crocker, J. G.
Object Type:
Report
System:
The UNT Digital Library
OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent activation energies of 50 kcal/mole in the absence of radiation and 30 kcal/mole in the presence of a 1 x 10/sup 6/ r/hr gamma flux. (auth)
Date:
July 1, 1961
Creator:
Dahl, R.E.
Object Type:
Report
System:
The UNT Digital Library
CASTING OF LONG AND THIN PLATES OF URANIUM-MOLYBDENUM ALLOYS
The development of procedures for the vacuum induction casting of U--Mo alloys into both thin (0.010 to 0.100-in. thick) plates and long (36 in.) plates is described. Melting and casting cycles were developed, and casting techniques established, which resulted in sound, integral plates. These plates were evaluated by radiographic and metallographic examination, and by chemical analysis. The results indicated the feasibility of the process for the fabrication of fuel plates for nuclear reactors. The process promises a potential reduction in fabrication costs, by eliminating waste. (auth)
Date:
November 1, 1961
Creator:
Katz, N.H. & Binstock, M.H.
Object Type:
Report
System:
The UNT Digital Library