587 Matching Results

Results open in a new window/tab.

The Brady Herald (Brady, Tex.), Vol. 19, No. 1, Ed. 1 Tuesday, October 31, 1961 (open access)

The Brady Herald (Brady, Tex.), Vol. 19, No. 1, Ed. 1 Tuesday, October 31, 1961

Weekly newspaper from Brady, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: Wilson, Bob
Object Type: Newspaper
System: The Portal to Texas History
Brenham Banner-Press (Brenham, Tex.), Vol. 96, No. 215, Ed. 1 Tuesday, October 31, 1961 (open access)

Brenham Banner-Press (Brenham, Tex.), Vol. 96, No. 215, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Brenham, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: Whitehead, Tom S., Jr.
Object Type: Newspaper
System: The Portal to Texas History
Brownwood Bulletin (Brownwood, Tex.), Vol. 62, No. 15, Ed. 1 Tuesday, October 31, 1961 (open access)

Brownwood Bulletin (Brownwood, Tex.), Vol. 62, No. 15, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Brownwood, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: Coppedge, Don L.
Object Type: Newspaper
System: The Portal to Texas History
The Calhoun County Times (Port Lavaca, Tex.), Vol. 7, No. 43, Ed. 1 Tuesday, October 31, 1961 (open access)

The Calhoun County Times (Port Lavaca, Tex.), Vol. 7, No. 43, Ed. 1 Tuesday, October 31, 1961

Weekly newspaper from Port Lavaca, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: unknown
Object Type: Newspaper
System: The Portal to Texas History
The Cesium-137 Power Program. Quarterly Report No. 3 (open access)

The Cesium-137 Power Program. Quarterly Report No. 3

Progress made in the development of the Cs/sup 137/ fueled thermoelectric generator for marine power applications is reported. Information is given on thermoelectric generator design, shielding, power conversion system, hazards evaluation, fuel element forming and cladding, fabrication, and heat transfer. Cs/sup 137/ energy calculations are presented along with shielding calculations. The development and fabrication of cesium polyglass for fuel application are included. (N.W.R.)
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, JUNE 1960 (open access)

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT FOR APRIL, MAY, JUNE 1960

7 9 7 D 8 8 9 9 7 7 ; 8 < fuel-reprocessing plant using pyrometallurgical procedures is being designed and constructed as part of the Experimental Breeder Reactor No. 2 project. Cable samples sealed with Temporell No. 741 were irradiated to 3.0 x lO/sup 9/ rad. Tests of the absorber-type fume trap were successful. Preparations were continued for high- activitylevel demonstrations of the melt-refining process for EBR-2 core fuel. An attractive and efficient procedure for removing uranium skull material from a melt-refining crucible is to convent it to free-flowing oxide powder by oxidation with a dilute oxygen- argon mixture at 700 to 800 deg C. Two complete runs were made for both demonstrating and pin-pointing difficulties in the drag-out or skullreclamation process. Investigation of the reduction of uranium oxides by liquid magnesium alloys was continued. Two runs were made to demonstrate recovery of plutonium from a magnesium solution by distillation of the magnesium. Operation of a mild steel corrosion loop for circulating a U-Mg- Cd alloy at 550 deg C was terminated after 4800 hr of trouble-free operation. The solubility of titanium in liquid cadmium was found to vary between 0.047 at.% at 449 deg C to 0.15 …
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY, FEBRUARY, MARCH 1961 (open access)

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY, FEBRUARY, MARCH 1961

8 7 < 6 ; : : = 8 g developed for recovering fissionable and fertile materials from shortcooled reactor fuels. The second laboratory demonstration of the melt-refining process with highly irradiated EBR- IItype fuel pins was completed. A 392-g charge of U-5% fissium fuel pins irradiated to an estimated burnup of 0.4 total at.% and cooled 28 days was melt refined for three hours at 1400 deg C. Data were not obtained on the behavior of fission products. The effect of N concentration on the nitridation rates of unirradiated U-fissium alloys in Ar-N atmospheres was determined. Experiments on the storage of fuel pins at 350 deg C in Ar atmospheres showed that the presence of 5% N lowered product yields only slightly during subsequent melt-refining operations. Supplementary pouring techniques, such as the use of probes and mashers designed to break crusts over the melts, are moderately effective, but are a less desirable solution to the problem of maintaining high yields than the elimination of contaminants in the Ar atmosphere. A liquid metal process is under development for recovery of the fissionable material contained in melt refining crucible skulls produced in the EBR-II fuel cycle. Information obtained in separate studies …
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Chickasha Daily Express (Chickasha, Okla.), Vol. 69, No. 209, Ed. 1 Tuesday, October 31, 1961 (open access)

The Chickasha Daily Express (Chickasha, Okla.), Vol. 69, No. 209, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Chickasha, Oklahoma that includes local, state and national news along with advertising.
Date: October 31, 1961
Creator: Drew, Charles C.
Object Type: Newspaper
System: The Gateway to Oklahoma History
Cleburne Times-Review (Cleburne, Tex.), Vol. 56, No. 299, Ed. 1 Tuesday, October 31, 1961 (open access)

Cleburne Times-Review (Cleburne, Tex.), Vol. 56, No. 299, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Cleburne, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: Proctor, Jack
Object Type: Newspaper
System: The Portal to Texas History
The Coleman Democrat-Voice (Coleman, Tex.), Vol. 81, No. 21, Ed. 1 Tuesday, October 31, 1961 (open access)

The Coleman Democrat-Voice (Coleman, Tex.), Vol. 81, No. 21, Ed. 1 Tuesday, October 31, 1961

Weekly newspaper from Coleman, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: unknown
Object Type: Newspaper
System: The Portal to Texas History
The Cuero Record (Cuero, Tex.), Vol. 67, No. 257, Ed. 1 Tuesday, October 31, 1961 (open access)

The Cuero Record (Cuero, Tex.), Vol. 67, No. 257, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Cuero, Texas that includes local, state and national news along with advertising.
Date: October 31, 1961
Creator: unknown
Object Type: Newspaper
System: The Portal to Texas History
The Daily News-Telegram (Sulphur Springs, Tex.), Vol. 83, No. 256, Ed. 1 Tuesday, October 31, 1961 (open access)

The Daily News-Telegram (Sulphur Springs, Tex.), Vol. 83, No. 256, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Sulphur Springs, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: Frailey, F. W. & Woosley, Joe
Object Type: Newspaper
System: The Portal to Texas History
Denton Record-Chronicle (Denton, Tex.), Vol. 59, No. 71, Ed. 1 Tuesday, October 31, 1961 (open access)

Denton Record-Chronicle (Denton, Tex.), Vol. 59, No. 71, Ed. 1 Tuesday, October 31, 1961

Daily newspaper from Denton, Texas that includes local, state, and national news along with advertising.
Date: October 31, 1961
Creator: unknown
Object Type: Newspaper
System: The Portal to Texas History
Deuterium-Hydrogen Exchange in Boehmite Corrosion Product Formed on Pure Aluminum in Boiling Water (open access)

Deuterium-Hydrogen Exchange in Boehmite Corrosion Product Formed on Pure Aluminum in Boiling Water

Proton-deuteron exchange is rapid in boehmite corrosion product formed on pure aluminum in boiling water. In addition, deuterated boehmite films undergo rapid exchange with the humidity of the atmosphere. This explains the previously reported anomaly in the H-D exchange rate for the growing corrosion product on 1100 aluminum. (auh)
Date: October 31, 1961
Creator: Mori, S.; Draley, J. E. & Bernstein, R. B.
Object Type: Report
System: The UNT Digital Library
Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Final Report, Phase I (open access)

Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Final Report, Phase I

Activities in a program to develop techniques of plasma spraying clad plate-type UO/sub 2/ fuel elements are reported. The investigation was also directed toward determining the limitations of the process as applied to fuel element fabrication. UO/sub 2/ powder coatings having densities of 90% theoretical were produced. At conditions required for spraying plates, densities of 86% appear to be practical. The rate and efficiency of UO/sub 2/ coating deposition were also determined for various spraying conditions. Gritblasting was found to provide the best surface for coating adherence. The O/U ratio of the UO/sub 2/ was maintained by spraying in an Ar atmosphere. Zircaloy-2 was found to be the most desirable cladding material. Cladding thicknesses of 0.035 in. are required in distortion-free 2-in.-wide plates. (J.R.D.)
Date: October 31, 1961
Creator: Weare, N. E.
Object Type: Report
System: The UNT Digital Library
Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Quarterly Technical Progress Report, January-March 1961 (open access)

Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Quarterly Technical Progress Report, January-March 1961

The development of plasma-jet spray-coating techniques for producing clad ceramic fuel plates is discussed. Conditions for spraying fused UO/sub 2/ powder were established by depositing cones on stationary substrates. It was found that the arc-gas flow range within which deposition occurs is very narrow. Coatings were made from --200 +325, --270 + 325, and de-slimed -325 mesh fused UO/ sub 2/ powders. To provide data regarding the economics of the process, deposition rates and efficiencies were determined under various conditions. The effects of powder size, power input, arcgas flow rate, spray distance, traverse rate, power feed rate, powder-gas flow rate, and cover-gas flow rate on deposition efficiency are discussed. Oxygen-to-uranium ratios of coatings made for evaluation of density were determined by gravimetric and volumetric methods. Preparation of the surface without distortion for plasma spraying is discussed. Fixturing and instrumentation methods were designed for measuring substrate and coating temperatures during spraying of typical fuel-element-cladding thickesses of stainless steel and Zircaloy-2. (M.C.G.)
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
DEVELOPMENT OF PLUTONIUM BEARING FUEL MATERIALS. Progress Report for Period April 1 through June 30, 1961 (open access)

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
ENVIRONMENTAL MONITORING REPORT, OCTOBER 1, 1960-DECEMBER 31, 1960 (open access)

ENVIRONMENTAL MONITORING REPORT, OCTOBER 1, 1960-DECEMBER 31, 1960

None
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, January-March 1961 (open access)

EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, January-March 1961

In this investigation, the effect of an ultrasonic field on the maximum nucleate heat flux (burnout) that can be sustained by boiling water in a flow system will be determined. The water will flow in the direction of sound propagation within an annular flow channel bounded on the outside by a glass tube and on the inside by a 0.25-in. OD heating element. The design of the test section and flow system is given. (D.L.C.)
Date: October 31, 1961
Creator: Romie, F.E.
Object Type: Report
System: The UNT Digital Library
The Fayette County Record (La Grange, Tex.), Vol. 39, No. 104, Ed. 1 Tuesday, October 31, 1961 (open access)

The Fayette County Record (La Grange, Tex.), Vol. 39, No. 104, Ed. 1 Tuesday, October 31, 1961

Semi-weekly newspaper from La Grange, Texas that includes local, state, and national news along with extensive advertising.
Date: October 31, 1961
Creator: Sulak, L. J.
Object Type: Newspaper
System: The Portal to Texas History
Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources (open access)

Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources

"Rates of acetylene polymerization induced by Kr/sup 85/ in d-c fields were up to 15 times greater than those observed when no fields were imposed. Work to determine the relations between acetylene pressure, Kr/sup 85/ concentration, and the field intensity is continuing. In other activities, equipment is being designed to study the effects of megacycle electric fields on radioinduced chemical reactions."
Date: October 31, 1961
Creator: Graessley, William W. & Zufall, John W.
Object Type: Report
System: The UNT Digital Library
Final Contract Report for September 1, 1959 to August 31, 1960 . (open access)

Final Contract Report for September 1, 1959 to August 31, 1960 .

"As presented in the original proposal the project consisted essentially of three parts: Phase I, Development and refinement of a radiochemical flow counting technique for the study of kinetics of reactions in solution ; Phase II, The application of this technique to the detailed study of the mechanism of solvolysis of sulfonium salts in mixed solvents ; Phase II, The further application of this kinetic technique, as a longer term aim, to other reacting systems of biochemical or other interest. This report covers the work of the contractual period 1 Sept. 1959 to 31 Aug. 1960."
Date: October 31, 1961
Creator: Hyne, James B.; Abrell, J. W.; Gurst, J. E. & Jacobson, Ada L.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961 (open access)

Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961

The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulation of a reactor as a feedback control system was adapted to VBWR. Equations for the hydraulics model and preliminary results from use of the model are presented. Irradiation of the Fuel Cycle stainless steel clad assemblies reached 412 MWD/T with specific powers of 28 kw/kg (average) and 52 kw/kg (peak) during January. Visual examination of the fuel after this irradiation indicated that it is in good condition. The VBWR was shut down during February and March for replacement of all in-core components made of 17-4 pH stainless steel with 304 stainless steel. The details of the first eight special fuel assemblies were determined and materials were ordered. The effects of steam quality, mass flow rate, and rod diameter on burnout heat flux are shown. The burnout heat flux varied inversely with mass …
Date: October 31, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH DEVELOPMENT PROGRAM. First Summary Report for March 1959-July 1960 (open access)

FUEL CYCLE PROGRAM, A BOILING WATER REACTOR RESEARCH DEVELOPMENT PROGRAM. First Summary Report for March 1959-July 1960

The Fuel Cycle Development Program is a basic development program for boiling and other water technology. It covers the areas of oxide fuel fabrication. irradiation. and examination; the physics of water-moderated reactore; and boiling-water heat transfer and stability. Schedules for the fuel- cycle program were examined. and it was concluded that portions of the Task A program should be conducted during the period May to Dec. 1959 in order to keep costs of the work as low as possible and to allow initiation of the fuel-cycle program at the earliest possible date after the Vallecitos BWR was returned to service. The basis for the scheduling of the work is discussed. and a chronological summary describing the content of the work is given. Technical progress is outlined and details are summarized. Subsequent reports issued monthly and quarterly will summarize the progress of the prognam. (W.D.M.)
Date: October 31, 1961
Creator: Cook, W.H.
Object Type: Report
System: The UNT Digital Library