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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading
A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date:
January 10, 1962
Creator:
Brondel, J. O.
Object Type:
Report
System:
The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962
The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedependent fracture occurred which could be definitely attributed to the delayed failure phenomenon; an increased grain size, 20% cold deformation by rolling, or corrosion in 750 deg F steam did not significantly affect this behavior. The curve of applied stress versus time to failure at room temperature for the high-strength Zr-Al-Sn--Mo alloy containing 500 ppm hydrcgen established a strong susceptibility to delayed failure due to hydrogen absorption; studies on vacuum-annealed material showed no failures. Further, reduced temperature indicated that the occurrence of static fatigue is temperature dependent. Data for heattreated Zr 2.5Nb containing 500 ppm hydrogen indicated that this material is moderately sensitive to delayed failure at room temperature; higher hydrogen contents caused a greatly increased susceptibility to time-dependent fracture. (auth)
Date:
October 10, 1962
Creator:
Weinstein, D. & Holtz, F. C.
Object Type:
Report
System:
The UNT Digital Library
REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM
Completion of zero-power critical experiments with the ORNL Health Physics Research Reactor is reported. A description is given concerning these experiments which were used to determine the critical size, fission-rate distributions, reactivity calibrations of its movable parts, the temperature coefficient of reactivity, and the reactivity effects of the presence of neutron- reflecting materials adjacent to the reactor. (J.R.D.)
Date:
May 10, 1962
Creator:
Mihalczo, J.T.
Object Type:
Report
System:
The UNT Digital Library
LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES
The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied from 0.2 to 0.00001, while the total normality of the system constituents was held constant. Results were plotted as equivalent fraction of the traced cation on the zeolite at equilibrium vs. the fraction of traced cation remaining in the equilibrium solution. If an influent composition is known, and falls in the system listed above, zeolite column loading may be read directly in univalent-univalent or divalent-divalent systems. However, in the strontium-sodium or strontium-- hydrogen systems, a k value must be used because squared terms appear in the equilibrium expression as follows: 2 Na- zeolite plus or minus Sr-solution in equilibrium 2 Nasolution + Sr-zeolite, or k = (Sr-zeolite)(Na-solution)/ (Na-zeolite)2(Sr-solution). The k for a given cation is a function of zeolite loading with that cation. Several column 50% loading capacities were determined to randomly test the validity of the above curves to predict column capacities, Several columns …
Date:
August 10, 1962
Creator:
Ames, L.L. Jr. & Knoll, K.C.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Technical Report on Spert Project, January-March 1962
None
Date:
August 10, 1962
Creator:
Schroeder, F.
Object Type:
Report
System:
The UNT Digital Library
TWO AUXILIARY CODES FOR USE WITH RENUPAK
Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date:
August 10, 1962
Creator:
Trubey, D.K.
Object Type:
Report
System:
The UNT Digital Library
NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR
Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date:
April 10, 1962
Creator:
Beyster, J R
Object Type:
Report
System:
The UNT Digital Library
INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II
ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date:
January 10, 1962
Creator:
Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Object Type:
Report
System:
The UNT Digital Library
The Ornl Analytical Chemistry Division's 150-Kv Cockcroft-Walton Generator
A general description of the facilities used to house a small Cockcroft- Walton generator is presented. Preliminary irformation and data are given as to the operational performance of the generator, the radiation safety controls involved, and the expected use of the device, In addition, an automatic-manual device for control of tritium target usage is described. (auth)
Date:
September 10, 1962
Creator:
Strain, J. E.; Hampton, W. J. & Leddicotte, G. W.
Object Type:
Report
System:
The UNT Digital Library
Numerical Analysis of Neutron Resonances
Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. Gauss' method was used to reduce the nonlinear problem to one in which linear methods can be applied. Some unusual techniques were used for evaluating the integrals in the function for calculating the transmission. Two programs for analyzing transmission data to obtain the parameters of the resonances were written for the IBM 7090 computer. The first program is a shape analysis for determining the resonant energies, the total widths, and the neutron widths of the resonances. This program analyzes the transmission data for as many as six resonances at once. The second program is an area analysis for determining the neutron widths of the resonances for assumed total widths. This program analyzes transmission data containing as many as 20 resonances at once. (auth)
Date:
January 10, 1962
Creator:
Atta, S.E. & Harvey, J.A.
Object Type:
Report
System:
The UNT Digital Library
IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY
Paper presented at American Nuclear Society Meeting, June I8-21, 1962, Boston, Mass. Design and operating problems of unclad and ceramic gas-cooled reactor fuels in high temperature circulating gas systems will be studied using a test facility now nearing completion at the Oak Ridge Research Reactor. A shielded air-tight cell houses a closed circuit gas system equipped for dealing with fission products circulating in the gas. Experiments can be conducted on fuel element performance and stability, fission product deposition, gas clean up, activity levels, component and system performance and shielding, and decontamination and maintenance of system hardware. (auth)
Date:
July 10, 1962
Creator:
Zasler, J.; Huntley, W. R.; Gnadt, P. A. & Kress, T. S.
Object Type:
Report
System:
The UNT Digital Library
OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source
A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date:
August 10, 1962
Creator:
Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Object Type:
Report
System:
The UNT Digital Library
THE FABRICATION AND IRRADIATION TESTING OF DISPERSION-TYPE BeO-UO$sub 2$ CERAMIC FUEL MATERIALS
Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol% UO/sub 2/ dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO --UO/sub 2/ ceramic fuel materials is described. From the results obtained, it is believed that BeO --UO/sub 2/ fuel materials of the type studied will exhibit satisfactory performance in the Experimental Beryllium Oxide Reactor. (auth)
Date:
October 10, 1962
Creator:
Johnson, D. E. & Lofftus, F. H.
Object Type:
Report
System:
The UNT Digital Library
Super-Prompt-Critical Behavior of an Unmoderated Unreflected Uranium- Molybdenum Alloy Assembly
The time-dependent behavior was investigated of the neutron population in an unreflected unmoderated cylindrical assembly of 90 wt.% U (93.2 wt.% U/sup 235/), 10 wt.% Mo alloy following rapid establishment of a super-prompt critical c ondition with negligible initial neutron population. Reactivity increases up to 11 cents above prompt critical resulted in bursts yielding as many as 1.8 x 10/ sup 17/ fissions with reactor periods as short as 16 mu sec and temperature increases as large as 400 deg C. Pressure waves generated in a portion of the core held in position by an electromagnet for bursts greater than ~6 x 10/sup 16/ fissions initiated the removal of this section about 225 mu sec after the peak burst. (auth)
Date:
May 10, 1962
Creator:
Mihalczo, J.T.
Object Type:
Report
System:
The UNT Digital Library
PL FINAL DESIGN REPORT. VOLUME VI. PLANT PERFORMANCE ANALYSIS
Data and information are presented concerning analyses of PL-2 transient performance, normal startup and shutdown procedures, and shield design. (J.R.D.)
Date:
May 10, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The Structures of NiZr$sub 2$, NiZr and Their Hafnium Analogs
None
Date:
March 10, 1962
Creator:
Kikpatrick, M. E.; Bailey, D. M. & Smith, J. F.
Object Type:
Article
System:
The UNT Digital Library
A Bench-Scale Natural-Recirculation Dissolver
A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated MTR fuel elements of 2-S aluminum ranged from 0.25 to 4.0 mg/(cm/sup 2/)(rain), depending on the catalyst concentration in the dissolvent and the dissolvent flow rate. For comparable catalyst and acid feed concentrations, dissolution rates, based on unit net superficial velocities, were nearly 25 times those for dissolution of randomly- packed flat plates in a pilot plant, continuous, flooded dissolver. (auth)
Date:
January 10, 1962
Creator:
Erickson, E. E.
Object Type:
Report
System:
The UNT Digital Library
DISCUSSION OF AN ACTIVATION METHOD FOR MEASURING THE RATIO OF U$sup 238$ ABSORPTION TO U$sup 235$ FISSION IN A REACTOR
The theory is presented in detail of an activation method for measuring the ratio of U/sup 238/ absorptions to U/sup 235/ fissions in a nuclear reactor. The origin of the activities is discussed, the equations are given for interpretation of the measurements, and the expected counting rates are computed for a typical experiment in the EGCR. (auth)
Date:
August 10, 1962
Creator:
Preskitt, C.A.
Object Type:
Report
System:
The UNT Digital Library
PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962
Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date:
April 10, 1962
Creator:
Humphries, G. E.
Object Type:
Report
System:
The UNT Digital Library
[Photograph 2012.201.B0363.0517]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Eddie Evans Oklahoma's tiny guard"
Date:
January 10, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0239.0694]
Photograph taken for a story in the Oklahoma Times newspaper.
Date:
December 10, 1962
Creator:
Matheson, Mandell
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0239.0693]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "SANTA CLAUS is coming to town, and any-one at the Women's Dinner Club meeting Monday night, who doesn't believe this, just wasn't listening"
Date:
December 10, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History
[Photograph 2012.201.B0300.0099]
Photograph taken for a story in the Oklahoma Times newspaper. Caption: "Setting for communion is this table in Sunnylane Methodist Church, Del City."
Date:
May 10, 1962
Creator:
Albright, Bob
Object Type:
Photograph
System:
The Gateway to Oklahoma History
BASEMENT BOX 67.0580
Photograph taken during daylight of a building in flames. Caption: "Fireballs visible in center and left of this photo were caused by exploding oxygen tanks in the shop building of Tonkawa Welding Works, Tonkawa, which was completely destroyed by fire Wednesday afternoon."
Date:
May 10, 1962
Creator:
unknown
Object Type:
Photograph
System:
The Gateway to Oklahoma History