2,012 Matching Results

Results open in a new window/tab.

Carbide Cathode Studies, Physical and Chemical Redeposition. Quarterly Progress Report, April 1, 1962-June 30, 1962 (open access)

Carbide Cathode Studies, Physical and Chemical Redeposition. Quarterly Progress Report, April 1, 1962-June 30, 1962

The utilization of physical and chemical processes to reduce the rate of vapor loss of thermionic emitters composed of mixed carbides of U and Zr in order to increase the permissible operating temperature is being studied. Preliminary, qualitative results obtained from study of physical redeposition processes showed that increasing the collector temperature may markedly reduce the rate of weight loss from a UC emitter operating at 2053 deg K. The requisite experimental equipment for studies of chemical transport processes was designed and constructed. Experiments will proceed through both a physical chemistry approach to an understanding of the transport processes and a technique to evaluate the efficacy of possible combinations of chemical species by monitoring the electron emission from diodes containing such mixtures. (auth)
Date: July 18, 1962
Creator: Weinberg, A. F.; Yang, L. & Langer, S.
Object Type: Report
System: The UNT Digital Library
The Effects of Irradiation on Uranium-Plutonium-Fissium Fuel Alloys. Final Report on Metallurgy Program 6.5.5 (open access)

The Effects of Irradiation on Uranium-Plutonium-Fissium Fuel Alloys. Final Report on Metallurgy Program 6.5.5

A total of 35 specimens of U-Pu-fissium alloy and 2 specimens of U-10 wt% Pu-5 wt% Mo alloy were irradiated as a part of the fue1-alloy development program for fast breeder reactors at Argonne National Laboratory. Total atom burnups ranged from 1.0 to 1.8% at maximum fuel temperatures ranging from 230 to 470 deg C. Emphasis was placed on the EBR-II Core-III reference fuel material, which is an injection-cast, U-20 wt% Pu-10 wt% fissium alloy. lt was found that this material begins to swell catastrophically at irradiation temperatures above 370 deg C. The ability of the fuel to resist swelling did not appear to vary appreciably with minor changes in Zr or fissium content. Decreasing the Pu to 10 wt%, however, significantly improved the swelling behavior of the alloy. Both pourcast and thermally cycled material and pour-cast, extruded, and thermally cycled material appeared to be more stable under irradiation than injection-cast material. Under comparable irradiation conditions, the specimens of U-20 wt% Pu- 5 wt% Mo alloy were less dimensionally stable than the U-Pu-fissium alloys investigated. (auth)
Date: July 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Dunworth, R. J.
Object Type: Report
System: The UNT Digital Library
A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962 (open access)

A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962

The effect of modifying the dislocation structure by room-temperature prestraining on the subsequent yielding behavior at 77 deg K is being studied. Results on tantalum single crystals indicated that a considerable decrease in the early yield stress for a given strain is effected by prestraining at room temperature. Twinning was observed in the tantalum at 77 deg K and normal rates of strain. It is shown that the potential barrler to dislocation motion in crystalline solids can be measured in relatively pure bcc transition metals such as Nb, Ta, Mo, and W. Work is being carried out to extend the method of differential calorimetry to measurements of stored-energy-release spectra in deformed bcc metals. Measurements for copper are discussed. (M.C.G.)
Date: July 25, 1962
Creator: Trozera, T.A.; Flynn, P.W.; Chambers, R.H. & White, J.L.
Object Type: Report
System: The UNT Digital Library
AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL (open access)

AN ESTIMATE OF THE EFFECT OF NEUTRON-ENERGY SPECTRUM ON RADIATION DAMAGE OF STEEL

The postulate that the average number of lattice displacements is directly proportional to the available energy is carried one step further; it is assumed that damage to steel (particularly in regard to brittle fracture) is proportional to the number of lattice vacancies that occur. The model, although crude, permits estimation of the relative damage resulting from differences in neutron spectra. The results can be used as a rough method of correcting damage data for the effect of the neutron-energy spectrum. Radiation damage calculations for steel, relative to those for a fission spectrum, were made for neutron spectra that result from fission neutrons penetrating water or graphite. The results were plotted as a function of effective distance from the fission source. From this plot it is possible to make a conservative estimate of the correction factor to apply to damage data obtained with different neutron spectra. (auth)
Date: July 27, 1962
Creator: Claiborne, H.C.
Object Type: Report
System: The UNT Digital Library
A GENERALIZED PROCEDURE FOR THE ISOLATION OF IODINE WITHOUT CARRIER--ITS DETERMINATION BY NEUTRON ACTIVATION USING I$sup 129$ AS AN ISOTOPIC TRACER (open access)

A GENERALIZED PROCEDURE FOR THE ISOLATION OF IODINE WITHOUT CARRIER--ITS DETERMINATION BY NEUTRON ACTIVATION USING I$sup 129$ AS AN ISOTOPIC TRACER

In order to make the 1.7 x 10/sup 7/-year I/sup 129/ useful as an iodine tracer, a neutron-activation procedure was used for its determination. A procedure involving high-temperature ignition in a stream of oxygen was devised for the isolation of iodine from a variety of materials. After activation and decontamination, a large sodium iodide, well-type crystal was used as a selective detector for the I/sup 130/ activation product. The normal iodine content of a sample is readily determined at the same time. (auth)
Date: July 1, 1962
Creator: Studier, M.H.; Postmus, C. Jr.; Mech, J.; Walters, R.R. & Sloth, E.N.
Object Type: Report
System: The UNT Digital Library
EFFECTIVE CUTOFF ENERGIES FOR B, Cd, Gd, AND Sm FILTERS (open access)

EFFECTIVE CUTOFF ENERGIES FOR B, Cd, Gd, AND Sm FILTERS

Effective energy cutoffs have been calculated on an IBM7090 computer for Cd, Gd, Sm, and B filters as functions of filter geometry, the ratio of Maxwellian to epithermal flux (assumed to be 1/E), the lower energy limit of the 1/E flux, the energy corresponding to the Maxwellian most probable (modal) velocity and filter thickness. The geometrical configurations were spherical (which on the assumptions madc is equivalent to a beam flux case), cylindrical and slab. By the use of two or three different filters (Cd and Gd and perhaps Sm) it should be possible to detect resonances in the thermal to cutoff energy regions, in addition to measuring resonance integrals and thermial cross sections of unknown nuclides. (auth)
Date: July 27, 1962
Creator: Stoughton, R.W. & Halperin, J.
Object Type: Report
System: The UNT Digital Library
"Life" Tests on Internally Water-Cooled Hollow Copper Conductors (open access)

"Life" Tests on Internally Water-Cooled Hollow Copper Conductors

Tests were conducted to determine whether a time limitation exists on the use of internally water-cooled hollow copper conductors operating at densities of up to 330,000 amps/in/sup 2/. Using demineralized water, having a specific resistivity of 4 to 9 x 10/sup 6/ ohm-cm, no indication of a decrease in heat transfer coefficient as a function of time was observed. However, metallographic examination revealed that corrosion--erosion does occur at a slow rate. Using process water there was a time dependent decrease in heat transfer coefficient and a consequent rise in metal temperature. The subsequent use of demineralized water in the same conductor again produced stable heat transfer, over the time spans investigated, 192 hours. The maximum total time investigated was 873 hours for one conductor. (auth)
Date: July 18, 1962
Creator: Lewin, J.
Object Type: Report
System: The UNT Digital Library
Temperature Coefficients of the Reactivity Measurement Facility (open access)

Temperature Coefficients of the Reactivity Measurement Facility

The temperature coefficient of the Reactivity Measurement Facility was found to be 49 plus or minus 1 mu k/ deg C (1 mu k = 10/sup -6/ DELTA k/k) in the range 15.4 to l7.8 deg C. The change in the net reactivity of a standard sample was --0.48 plus or minus 0.02, --0.66 plus or minus 0.03, and --0.78 plus or minus 0.02 mu k/ deg C in three measuring positions. These low values generally make temperature corrections insignificant. The above results are compared with previous determined values. This information developed in the RMF should be generally applicable to flux-trap-type reactors such as the Advanced Reactivity Measurement Facility (ARMF) and ARMF-ll, now under construction. RMF was dismantled in April 1962. (auth)
Date: July 27, 1962
Creator: Fast, E.
Object Type: Report
System: The UNT Digital Library
RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report No. 13 (open access)

RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report No. 13

Research was continued during the report period on the use of isotope neutron sources for producing short-lived radioisotopes. Experiments with a newly constructed betacounting cell are reported in which a 50-curie Be--Po neutron source was used. Study of the radiation chemistry of polymers was continued concerning the effects of polymer structure on free-radical formation. Free-radical formation in several additional polymers was studied. Preliminary work is also reported in an investigation of internal irradiation effects on the chemical activity of catalysts. (J.R.D.)
Date: July 19, 1962
Creator: Sunderman, D.N. ed.
Object Type: Report
System: The UNT Digital Library
Fuel Cycles and Loading Programming for Water-Cooled Research Reactors (open access)

Fuel Cycles and Loading Programming for Water-Cooled Research Reactors

The problems encountered while developing loading methods for the ORNL water-cooled research reactors are discussed. The methods used to program the fuel loading for the LITR and ORR are described as well as the experimental methods that produced the data necessary for the solution of these problems. (auth)
Date: July 31, 1962
Creator: Colomb, A. L. & Cavin, D.
Object Type: Report
System: The UNT Digital Library
PERSONNEL-EXPOSURE AND CONTAMINATION CONTROL IN THE ROUTINE OPERATION OF THE ORNL RESEARCH REACTORS (open access)

PERSONNEL-EXPOSURE AND CONTAMINATION CONTROL IN THE ROUTINE OPERATION OF THE ORNL RESEARCH REACTORS

ABS>Measures are outlined that are taken to control occupational radiation exposure incurred in the routine operation of a reactor and in the conduct of activities associated with its operation. Those measures taken to minimize the frequency and effects of minor radiation and contamination incidents are also discussed. (C.H.)
Date: July 31, 1962
Creator: Sims, T.M.
Object Type: Report
System: The UNT Digital Library
POSSIBLE IMPLICATIONS OF THE DAMAGE BY RADIATION IN THE STORAGE OF PROPELLANTS IN OUTER SPACE AND TENTATIVE METHODS FOR ITS MEASUREMENT (open access)

POSSIBLE IMPLICATIONS OF THE DAMAGE BY RADIATION IN THE STORAGE OF PROPELLANTS IN OUTER SPACE AND TENTATIVE METHODS FOR ITS MEASUREMENT

The damage by radiation that can be expected during the storage of H/sub 2/-bonded propellants in outer space is analyzed in terms of the available data on radiation levels. On this basis, the alternatives of storing the propellants as liquids or as solids, at low temperature, are discussed, and account is taken of recent results on their thermal behavior. Vitreous aggregation states of compounds that could crystallize spontaneously after long periods of irradiation are shown to present some hazards that can be prevented. General considerations of radiation-damage detection in outer space are also made. Paramagnetic resonance is found to be of little use in view of the relatively low-dose levels. Solid-state devices are recommended. (auth)
Date: July 1, 1962
Creator: McMillan, J.A.
Object Type: Report
System: The UNT Digital Library
Extraction of Niobium-95 From Nitric Acid Solutions With Tri-N-Butyl Phosphate (open access)

Extraction of Niobium-95 From Nitric Acid Solutions With Tri-N-Butyl Phosphate

The distribution coefficient (DC o/a) of Nb/sup 95/ between aqueous nitric acid and 30% Tri-n-butyl phosphate (TBP) in n-dodecane increased from ~0.004 to O.1 N acid deficient solution to 0.05 in 4 M HNO/sub 3/ for the extractable portion of the niobium. Greater than 70% of the niobium was unextractable. The presence of 3% chemically degraded TBP, 7% chemically degraded Amsco, or both decreased the amount of unextractable niobium to <20% and degraded TBP increased the distribution of the extractable portion. The aqueous solubility of the niobium extractant in the degraded reagents varied inversely with the acidity of the aqueous phase. The maximum DC o/a from acid deficient solutions containing solvent degradation products was ~0.008. The organic to aqueous DC o/a were higher than the aqueous to organic values for all solutions examined. Niobium retention was maximum by solvents containing both degraded TBP and Amsco, increasing from 6% to ~50% as the aqueous acidity decreases from 5 to O.1 M HNO/sub 3/. Nb/sup 95/ was removed from nitric acid solutions containing 20 g/liter Zr and Zr/sup 95/ by adsorption on unfired Vycor glass. (auth)
Date: July 1, 1962
Creator: Moore, J. G. & Rainey, R. H.
Object Type: Report
System: The UNT Digital Library
Surface Ionization Method of Detecting Halogen-Bearing Gases (open access)

Surface Ionization Method of Detecting Halogen-Bearing Gases

In an experimental investigation of positive ion production at heated surfaces, the primary objective was to develop a stable quantitative detector suitable for studies of movements of a gaseous tracer in the atmosphere or other large gaseous masses. Freon-12 (dichlorodifluoromethane) is well qualified as a tracer, srnce it is harmless to animals, plants, and equipment under ordinary conditions, is undetectable, except by special apparatus, and is not too expensive, considering that 0.1 ppm may be detected. Two phases of the work are discussed: the modification of a commercial detector to improve its reproducibility, and the investigation of the mechanism responsible for halogen sensitivity. A multiple-step process is involved. Steps studied included thermal decomposition of the Freon, release of alkali from a heated source and transfer through the carrier gas to a surface at high temperature, ionization, and ion collection by an electric field. Sensitivity may be lost by raising the halogen concentration enough to make ronization or ion collection the rate- controlling step, and this change is not immediately reversible. (auth)
Date: July 1, 1962
Creator: Schultz, H.A.
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B0229.0126]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Ralph A. Clinton, 3132 NW 52, has been named sales and merchandising manger for Scrivner-Stevens, also a newly-created position."
Date: July 22, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0318.0605]

Photograph taken for a story in the Oklahoma Times newspaper. Caption: "NEW CHARTER of All-Indian Tribe Confederation Club of Oklahoma is admired by Seminole chief Abraham Davis and Allen R. Dyson, one-eighth Comanche, and founder of the club."
Date: July 26, 1962
Creator: Matheson, Mandell
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0241.0545]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Mrs. Linda Hubler and Mrs. John Wilson Cory"
Date: July 25, 1962
Creator: Albright, Bob
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0408.0269]

Photograph taken for a story in the Oklahoma Times newspaper. Caption: "New Buildings at State Fairgrounds."
Date: July 6, 1962
Creator: Miller, Joe
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0316.0722]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Larry Osterhout, 12, gets around in a mode of transportation popular 50 years ago"
Date: July 19, 1962
Creator: Garner, Frank
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0290.0142]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Seattle-bound with 90 of their original 99 silver dollars are Mr. and Mrs. L. J. Dancey, a Tennessee couple in Oklahoma City Thursday."
Date: July 19, 1962
Creator: Matheson, Mandell
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0237.0469]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company.
Date: July 12, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0320.0215]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "is Tim Edwards, Kansas Highway Patrol trooper after he captured man and girl sought in shooting death of City Marshal Al Claycamp."
Date: July 19, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0235.0318]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Latest of the 15 distinguished jurors brought to Oklahoma City to decide the Bloch Young Artist Award are tenor Eugene Conley, Denton, Texas; Mrs. Hazel Post Gillette, Fort Worth; Hans Schwieger, Kansas City."
Date: July 25, 1962
Creator: Matheson, Mandell
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0051.1542]

Photograph taken for a newspaper owned by the Oklahoma Publishing Company. Caption: "Crumpled remains of Billy Fields' wrecked car."
Date: July 30, 1962
Creator: King, Cliff
Object Type: Photograph
System: The Gateway to Oklahoma History