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UNT Libraries Government Documents Department
11,870
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86
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24
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9
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6
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2
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1
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1
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Office of Scientific & Technical Information Technical Reports
10,274
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795
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418
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279
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100
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96
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86
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64
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13
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Atomic Energy Commission Reports
95
Personal Papers (MS 80-0002)
83
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55
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50
United States Department of Energy Grand Junction Office Reports
39
CRS Issue Briefs
28
AEC research and development report
20
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303 More
Country
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Decade
Day
Language
FINAL STATES WITH THREE CHARGED PARTICLES AND A VISIBLE $lambda$ FROM K$sup -$d INTERACTIONS AT 4.5 GeV/c
None
Date:
December 31, 1972
Creator:
Ammann, A. C.; Carmony, D. D.; Garfinkel, A. F.; Gutay, L. J.; Miller, D. H. & Yen, W. L.
System:
The UNT Digital Library
Production of K$sup +$K$sup -$ and p anti-p Pairs in Four-Body Reactions at 13.1 GeV/C
None
Date:
August 31, 1971
Creator:
Gaidos, J. A.; Mulera, T. A.; Ezell, C.R.; Lamsa, J.W. & Willmann, R.B.
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Topical Report for Task Ii. Development of Adsorption Reservoir. Period Covered: May 1, 1968--February 28, 1969.
This report covers work performed on the development of an integral adsorption reservoir thermionic converter.
Date:
October 31, 1969
Creator:
Freggens, R.A.
System:
The UNT Digital Library
EQUIPMENT AND TECHNIQUES FOR MEASUREMENTS OF THERMAL CONDUCTIVITY, THERMAL EXPANSION, AND ASSOCIATED PROPERTIES ABOVE 1000$sup 0$C.
None
Date:
October 31, 1969
Creator:
Wagner, P.
System:
The UNT Digital Library
RECOIL STUDIES IN CHEMICAL DYNAMICS. Progress Report, January 1, 1968-- December 31, 1968.
None
Date:
October 31, 1969
Creator:
unknown
System:
The UNT Digital Library
Radicals in Irradiated Crystals Studied by ESR Spectroscopy. Technical Report, January 1--December 31, 1967
None
Date:
August 31, 1968
Creator:
unknown
System:
The UNT Digital Library
SAVANNAH RIVER LABORATORY ISOTOPIC POWER AND HEAT SOURCES. PART I. $sup 60$Co. Quarterly Progress Report, October--December 1967
None
Date:
October 31, 1968
Creator:
Hilborn, H. S.
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.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
THE OAK RIDGE GASEOUS DIFFUSION PLANT FUEL REPROCESSING PROGRAM.
None
Date:
October 31, 1969
Creator:
Merriman, J.R. & Pashley, J.H.
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
System:
The UNT Digital Library
Control Characteristics of Rankine Cycle Systems Which Simulate the Mpre Fluid System.
In conjunction with the Medium power Reactor Experiment Program at ORNL, studies were conducted on two single-loop Rankine cycle systems. These systems were controlled using the same design concept which has been proposed for control of the MPRE fluid system. Experiments were run with water and potassium test facilities which were reduced scale electrically heated mockups of the proposed reactor and power recovery system. Results from these studies demonstrate that with proper design, the distribution of liquid inventory within the system can be controlled by the degree of cavitation occurring in the turbine-driven centrifugal boiler feed pump. Boiler power changes were made over a wide range and no operator action was required. The changes in fluid flow requirements were accommodated by a variation in the degree of pump cavitation occurring. Step changes in power were imposed on the boiler and there was no indication of instabilities in the fluid system.
Date:
October 31, 1969
Creator:
Yarosh, M.M.
System:
The UNT Digital Library
Nuclear Engineering Department Annual Report, December 31, 1968.
None
Date:
October 31, 1969
Creator:
unknown
System:
The UNT Digital Library
UNLV Information Science Research Institute quarterly progress report
This report presents research on information systems, information retrieval, and optical character recognition. (CBS)
Date:
December 31, 1991
Creator:
Nartker, T.A.
System:
The UNT Digital Library
Advanced Heat Pipe Thermionic Technology. Task I. Development of High Voltage Module. Mid-Term Status Report, May 1, 1968--February 28, 1969.
This report addresses he design of a heat pipe-thermionic module concept capable of output potentials as high as 28 volts.
Date:
October 31, 1969
Creator:
Longsderff, R.W.
System:
The UNT Digital Library
FUELS, MATERIALS, COOLANT CHEMISTRY, AND FUEL HANDLING PROGRAMS. Quarterly Technical Progress Report, October--December 1971
None
Date:
December 31, 1972
Creator:
unknown
System:
The UNT Digital Library
Zircaloy-Clad UO2 Fuel Rod Evaluation Program. Quarterly Progress Report Nos. 6 and 7, February--July 1969
None
Date:
December 31, 1969
Creator:
Megerth, F. H.
System:
The UNT Digital Library
Curium Process Development. III-7. Emission Spectrographic Determination of Metallic Impurities in Curium Oxide and Mixed Curium--Americium Oxide
None
Date:
December 31, 1971
Creator:
Gaddy, R. H.
System:
The UNT Digital Library
PROCEEDINGS OF THE NATIONAL TOPICAL MEETING ON FAST REACTOR SYSTEMS, MATERIALS, AND COMPONENTS, CINCINNATI, OHIO, APRIL 2--4, 1968.
None
Date:
October 31, 1969
Creator:
Niemuth, W.E. & Weissenberg, J.F. (eds.)
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
System:
The UNT Digital Library
Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix C: preliminary design data package. Volume I
The assumptions made, analysis methods used, and preliminary results of research to determine the design specifications for a hybrid electric-powered and internal combustion engine-powered vehicle that would optimize the fuel economy of passenger automobiles are described. Information is included on body and component design, selection of spark-ignition engine and Ni-Zn batteries, life-cycle costs and life-cycle fuel consumption. (LCL)
Date:
July 31, 1979
Creator:
Piccolo, R.
System:
The UNT Digital Library
ORGANIC WORKING FLUID BOILER INVESTIGATION. AEC ORGANIC RANKINE CYCLE TECHNOLOGY PROGRAM TOPICAL REPORT.
None
Date:
October 31, 1969
Creator:
Martz, J.L.
System:
The UNT Digital Library
An Exploratory Study of the Behavior of Niobium- and Vanadium-Base Alloys in Oxygen-Contaminated Sodium
None
Date:
December 31, 1968
Creator:
Levin, H. A. & Greenberg, S.
System:
The UNT Digital Library
Terrestrial photovoltaic power systems with sunlight concentration. Progress report, January 1, 1975--July 31, 1975
None
Date:
July 31, 1975
Creator:
unknown
System:
The UNT Digital Library