Partner
Oklahoma Historical Society
205
UNT Libraries Government Documents Department
95
UNT Libraries Special Collections
50
Rosenberg Library
21
Hardin-Simmons University Library
16
Abilene Public Library
7
Hopkins County Genealogical Society
7
Mount Pleasant Public Library
7
Oklahoma Conservation Historical Society
7
Sterling Municipal Library
7
88 More
Collection
Texas Digital Newspaper Program
158
Oklahoma Publishing Company Photography Collection
155
Office of Scientific & Technical Information Technical Reports
79
Tocker Foundation Grant
72
Oklahoma Digital Newspaper Program
51
KXAS-NBC 5 News Collection
34
Abilene Library Consortium
26
Ladd & Katherine Hancher Library Foundation
22
Harris and Eliza Kempner
21
The Oklahoma City Times
20
119 More
Country
States
Decade
Year
Day
Language
565 Matching Results
Results open in a new window/tab.
Results:
1 - 24 of
565
next
ANNUAL REPORT ON PHYSICAL SCIENCES, ENGINEERING AND LIFE SCIENCES , JULY 1, 1961
The research program at Brooknaven is described. Current activities in physics, high-energy accelerators, instrumentation, chemistry, nuclear engineering, applied mathematics, biology, and medical research are outlined. (D.L.C.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES
The accident experience of the AEC contractor operation for 1959 and 1960 is reported. Incidents involving radio active materials are described. A table of inadvertent criticality was included to supplement other tables. A tabulation of exposure records at values from 0 to 15 r is given. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
NUCLEAR SUPERHEAT PROJECT TENTH QUARTERLY PROGRESS REPORT, OCTOBER-DECEMBER 1961
Results in the Nuclear Superheat Project are summarized. Topics covered include: conceptual design and program evaluation, fuel technology, materials development, experimental physics, coolant chemistry, heat transfer, mechanical development, SADE and E-SADE, and mixed spectrum superheat study. (M.C.G.)
Date:
October 31, 1962
Creator:
Pennington, R.T.
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 No. 3, April-June 1961
The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JULY, AUGUST, SEPTEMBER, 1961
Development activities are reported on pyrometallurgical processes including melt refining and those using liquid metal solvents. Development of processing facilities for EBR II is also reported. In other work, laboratory- and engineering-scale investigations on fluoride volatility processes were condueted, and conversion of UF/sub 6/ to UO/sub 2/ was studied. Investigations are also reported concerning the kinetics of metal ignition and oxidation, and metalwater reactions. In work associated with reactor chemistry, data on nuclear constants are reported and developments in thermoelectricity and reactor decontamination are described. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SNAP Radioisotope Space Programs Quarterly Progress Report No. 9, October 1 Through December 31, 1961
All Phase I and Phase II testing was completed. Both launches of Phase I were successful, neither Phase II launches were successful. Test data recovered on Phase I launchings included optical coverage of re-entry and the trajectory and weather data; no telemetry canister temperature data were obtained. No test data were obtained on Phase II experiments. Reduction of Phase I test data was begun. The Phase II (Sub-subtask 7.3.2) was terminated December 20, 1961, when no test data were recovered for comparison with the analytically predicted results. The Sub-subtask 7.3.3 program (Generator Re-entry Burnup Study) was completed and terminated December 29, 1961. The study objectives were met. The Sub-subtask 7.3.4 program (High Altitude Sampling) was terminated when it was completed November 30, 1961. All study objectives were met. Topical reports were prepared on Sub-subtasks on the work performed in the reporting period that was not included in the topical reports is included. Checkout and troubleshooting operations on the last two subroutines and main radioisotope shielding code were completed. Results from several runs of a simple check problem compared well with published data. (auth)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
GAUGE FOR MEASURING BOW OF TUBES
A mechanical gage was designed to measure the bow over any one-foot length of long cylindrical material. The gage was used successfully for measuring bow in components of tubular fuel elements at the Savannah River Laboratory. (auth)
Date:
October 31, 1962
Creator:
Alewine, G.B.
Object Type:
Report
System:
The UNT Digital Library
Research in Radiobiology. Annual Report of Work in Progress on the Chronic Toxicity Program
Separate abstracts were prepared on 8 sections of this report. Data are also included on the status of dogs at various time intervals following the injection of various doses of Ra/sup 226/, Pu/sup 239/, Ra/sup 228/, Th/sup 228, and Sr/sup 90/. (C. H.)
Date:
March 31, 1962
Creator:
Dougherty, T. F.
Object Type:
Report
System:
The UNT Digital Library
SNAP 7 Program--Task 8--Strontium-90 Fueled Thermoelectric Generator Development. Quarterly Progress Report No. 5, November 1, 1961 to January 31, 1962
The SNAP 7A battery and converter were subjected to the required shock, vibration and temperature teats. The generator was fueled, postfueling radiation levels were checked and the generator was integrated into the complete SNAP 7A system. After the completion of acceptance tests, the SNAP 7A system was installed in a buoy which, in turn, was anchored in the bay where it will be subjected to further evaluation. The SNAP 7C generator was shipped for transport to Antarctica. The generator will power a five-watt U. S. Navy remote weather station. Tests were also conducted to determine the operational characteristics of SNAP 7B and 7D thermoelectric couples. Also, the reliability model of the generator was operated at high temperature for 23 days. The electrical, converter and battery specifications for the SNAP 7D system were completed and released. The primary effort in the fael processing phase of the program was to provide the necessary liaison with the personnel installing the processing equipment. Maintenance and checkout guides were written to assure satisfactory installation and continued performance throughout the fuel processing span. An operation procedure guide was written to describe the engineering concept of the fuel processing operation. The guide was written for the personnel …
Date:
October 31, 1962
Creator:
McDonald, W. A.
Object Type:
Report
System:
The UNT Digital Library
SNAP Programs: Task 6--Fuel Technology Development Program. Quarterly Progress Report No. 7, April 1 Through June 30, 1961
Progress made in the development of isotope power sources for thermoelectric and thermionic conversion to electrical energy is reported. The Heavy Elements Processing Facility for processing americium and fabricating americium capsules for irradiation was opened and hot operation was begun. Modifications to the americium purification system were completed and checkout operations were begun. Process specifications were established for dissolution of the irradiated capsules and the major equipment for this operation was designed. Experimental work on the purification of curium was continued. Blending and crushing studles were conducted to establish techniques and procedures for preparing curium carbide and for producing homogeneous cermet fuel forms. Investigations were also made into the compatibility of various matrix and container materials with curium carbides and oxides. Flow diagrams for the fuel form and isotope encapsulation processes were completed. A safety analysis was conducted which verified the integrity of the americium capsules during all stages of the irradiation program. (auth)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report, October 1-December 31, 1961
Continued effort is reported on preparation and characterization of PuO/ sub 2/ and UO/sub 2/-- PuO/sub 2/ mixtures. Sintering and characterization of pellets for irradiation tests was emphasized, and efforts were also devoted to plasma torch production of spherical PuO /sub 2/ and coating of oxide materials. PuO/sub 2/ produced by the oxalate process from low concentration feed contains agglomerates which are not readily broken down, while that produced from normal feed contains larger agglomerates which are easily dispersed ultrasonically, and are more easily calcined. The water filtration method for determining total porosity of powders was adapted for use with PuO/sub 2/. Moisture pickup studies show that the problems encountered with PuO/sub 2/ are similar to those found in handling ceramic-grade UO/. Reproducibility tests carried out on UO/sub 2/--PuO/ sub 2/ mixtures indicate that production methods are satisfactory. Lab-scale experiments on production of PuO/sub 2/-- UO/sub 2/feed for the plasma torch indicate that further work is worthwhile. Adaptation of a potentiometric filtration for Pu is reported. A twophase microstructure found in PuO/ after sintering in N6% H atmosphere was identified as PuO/sub 2/ and cubic Pu/sub 2/O/ sub 3/. Spherical particles were produced in the plasma torch using crushed or …
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
DEVELOPMENT OF PLUTONIUM-BEARING FUEL MATERIALS. Progress Report for Period January 1 through March 31, 1962
During this reporting period, particular effort was of aced on powder blending and pellet sintering studies prior to irradiation sample fabrication, and, subsequently, the production and characterization of the pellets slated for irradiation. Also, PuO/sub 2/ and UO/sub 2/-PuO/sub 2/ characterization studies were continued, and new techniques are being developed. Specifically, dynamic moisture pickup determinations on PuO/sub 2/ were made in moist air, N, and CO/ sub 2/ atmospheres using a recording thermogravimetric balance; the Sharples Micromerograph was committed to Pu, and powder particle size distributions were measured and compared with previous determinations made with air-permeability equipment; and the suitability and reliability of analytical chemistry assaying procedures such as x-ray-fluorescence and gamma spectrometry are being evaluated. Prototype work on UO/sub 2/ for the direct precipitation of PuO/sub 2/ and PuO/ sub 2/-UO/sub 2/ feed materials for swaging, vibratory compaction, and dispersion fabrication was also continued. In addition, investigation of PuO/sub 2/ spherical particle formation by mechanical buildup and by plasma torch fusion was extended. Associated reactor physics studies were concentrated on the further comparison of Pu and U/sup 235/ in near-thermal converter reactors. In preparation for the fabrication of irradiation test specimens to be prepared by the mechanical blending of …
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1961
Studies are reported on aqueous zirconium processing, dissolution of BeO- UO/sub 2/ ceramic fuel, the aqueous stainless steel process, the behavior of dibutyl phosphates, use of boron (boric acid) solution to assure critical safety, fluidized bed calcination, conversion of amorphous alumina to alpha alumina, the Demonstrational Waste Calcining Facility, removal of long-lived radioisotopes from waste solutions, separation of iron, nickel, and chromiun from stainless steel waste solutions, electrolytic dissolution, effects of stray currents, electrolytic disintegration of Zircaloy-2, corrosion evaluation of materials of construction, the ARCO process, a direct air pulsed extraction column, and large vessel criticality control. (M.C.G.)
Date:
October 31, 1962
Creator:
Bower, J. R.
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report, February-March 1962
Progress is reported in experimental nuclear physics on calculations concerning the distribution of lifetimes of neutrons in glass scintillation neutron detectors and on the probabilities for single, double, and triple scattering of neutrons in thin plates. Precision measurements of gamma-ray energies and intensities were used to modify and extend the level scheme of Hf/ sup 178/. The presence of three K = 0 rotational bands (besides the ground state) and two K = 2 rotational bands are indicated in the level scheme of this isotope. In other work the fluorescence properties of polystyrene were found to depend on concentration of residual styrene monomer and the average molecular weight. Research is also reported in theoretical physics on dynamics of nuclear collective motion, scatter ing of alpha particles by a vibrational nucleus, flux quantization and time-reversal degeneracy, and elastic nucleonnucleon scattering at high energies and small angles. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Physics Division Summary Report, April-May 1962
None
Date:
October 31, 1962
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, October-December 1960
>The effects of an ultrasonic field on the maximum nucleate heat flux that can be sustained by boiling water in a flow system are being investigated. Design and procurement of apparatus is underway. (M.C.G.)
Date:
October 31, 1962
Creator:
Romie, F.E.
Object Type:
Report
System:
The UNT Digital Library
IDAHO DIVISION SUMMARY REPORT, APRIL THROUGH SEPTEMBER 1961
Research and development progress is reported on TREAT, BORAX V, ZPR- III, EBR-II, and the reactor operations personnel training program. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
RADIOISOTOPE FUELED AUXILIARY POWER UNIT. Quarterly Progress Report No. 1, January 2-April 2, 1957
Progress on an isotope-fueled auxiliary power unit is reported. Based on the power requirements of 260 W, it was concluded that Ce/sup 144/ should be used as fuel. Estimates were made of fuel availability and unit cost and weight at power levels of 133, 300, 500, and 1000 W(e). Fuel development, boiler development, system and operational considerations, and the power conservation system are discussed. (M.C.G.)
Date:
October 31, 1962
Creator:
Silverstein, C.C. & Behmer, R.E. comps.
Object Type:
Report
System:
The UNT Digital Library
Pathfinder Atomic Power Plant Analog Simulator.
The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; moderated and cooled with saturated, light water; pressurized between 400 and 800 psiai and has a neutron flux distribution that is spatially invariant. All the importanit non-linearities are retained, thus permitting accurate solutions of large system disturbances. The neutron kinetics equations, with their six groups of delayed neutrons, are simulated with power feedbacks through reactor pressure, steam flow, core inlet subcooling, and fuel- element temperature. Particular attention ls devoted to the accurate simulation of fuel-element heat transfer; the reactor pressure-control system, which operates the turbine inlet valves; and the effect of core inlet subcooling, sinee these were found to have pronounced effects on reactor performance. The transient temperatures at the superheater hot spot and exit are generated. Enough flexibility ss included, so that all important disturbanees possible in the actual plant can …
Date:
January 31, 1962
Creator:
Crimmins, D. H.; Mohr, D. & Stone, J. T.
Object Type:
Report
System:
The UNT Digital Library
METALLURGY DIVISION ANNUAL REPORT FOR 1961
8 < 8 7 8 7 < 5 8 6 ; : 9: 2 8 9 9 ; ; < 9 : 9 : 8 8 I of transformation and fusion, of U and U- fissium alloys were completed during the year. Data are also included on cladding penetration by molten U-fissium alloys and molten Pu fuel. Irradiation studies of U-fissium and Ufissium-Zr alloys were conducted. Progress is reported on the development of methods and equipment for remote refabrication of EBR-II fuel. Development and Fabrication of EBR-I Core IV Fuel Elements. A program to investigate methods of fabricating Pu-Al reference alloy for EBR-I Core IV is described along with the production of fuel rods for this core. The procurement, fabrication, and inspection of components other than Ra material for Core N of EBR-I was continued. Data obtained in nondestructive inspection of EBR-I Core IV components are presented along with data concerning properties of and radiation effects on Al-Pu alloys. EBWR Fabrication Programs. The work in these programs was largely concenned with fabrication of a control-rod-drive assembly made of 17- 4 PH stainless steel. Fabrication of Borax-V Boiling and Superheater Fuel Elements, Control Rod Drive Shafts, and Control Rods. Data are …
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
IDO REPORT ON THE NUCLEAR INCIDENT AT THE SL-1 REACTOR, JANUARY 3, 1961 AT THE NATIONAL REACTOR TESTING STATION
A summary of activities which took place following an incident at the SL- 1 is presented. No attempt to determine the incident cause is included. A brief description of the SL-1 and the operating program in progress prior to the incident is given along with detailed information on various aspects of the past incident developments. (J.R.D.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, July-September, 1961
Bar-extrusion tests were performed at 50. 65, and 80% reductions at room temperature and 300 deg C. Tensile tests were conducted on as-extruded and heat-treated specimens. The results are tabulated for comparison. The extrusion of small tubing, 0.560-in. OD x 0.030-in. wall, in the first and second tube- extrusion steps are described. (B.O.G.)
Date:
October 31, 1962
Creator:
Weil, F.E. & Hill, J.G.
Object Type:
Report
System:
The UNT Digital Library
BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant
An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date:
October 31, 1962
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
SECOND SYMPOSIUM ON PHYSICS AND NONDESTRUCTIVE TESTING, HELD AT ARGONNE NATIONAL LABORATORY OCTOBER 3-5, 1961
Thirteen papers are included; separate abstracts have been prepared for each. Abstracts of two papers on some optical and electrical properties of materials and nondestructive testing of reactor irrcdiated metals are also included. These two abstracts are not included in NSA. (N.W.R.)
Date:
October 31, 1962
Creator:
di Novi, R.A. ed.
Object Type:
Report
System:
The UNT Digital Library