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Office of Scientific & Technical Information Technical Reports
1,338
USGS Topographic Map Collection
337
Texas Attorney General Opinions
223
Technical Report Archive and Image Library
81
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62
Congressional Research Service Reports
12
Advisory Commission on Intergovernmental Relations
7
Federal Communications Reports
4
Boy and Girl Scout Annual Reports
2
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7.5 Minute Series (Topographic)
250
Digital Raster Graphic Topographic Maps: 7.5 Minute Series (Topographic)
63
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24
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15
Office of Saline Water Reports
14
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12
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12
The Cross Section
12
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10
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2,074 Matching Results
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MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER.
None
Date:
January 1, 1966
Creator:
Gerhardstein, L.H.
Object Type:
Report
System:
The UNT Digital Library
DEEP SEA RADIOISOTOPE-FUELED THERMOELECTRIC GENERATOR POWER SUPPLY SYSTEM. SNAP-21B PROGRAM, PHASE I. Final Summary Report.
None
Date:
January 1, 1966
Creator:
Benson, D.; Panneman, R. & Yanisch, V. Jr.
Object Type:
Report
System:
The UNT Digital Library
Compensation for Victims of Crimes of Violence
This report details the compensating schemes of victims of comes of violence. It was announced on June 24, 1964, and came into operation on August 1, 1964.
Date:
May 31, 1966
Creator:
Price, Hugh P.
Object Type:
Report
System:
The UNT Digital Library
Precedents of the House of Representatives in Respects to Procedure for Censure or Expulsion, 1966
This report contains the procedure and outlines of investigating issues caused by elected officials of government.
Date:
December 29, 1966
Creator:
Tienken, Robert L.
Object Type:
Report
System:
The UNT Digital Library
The Draft: Miscellaneous Materials Related to Selective Service and Some Proposed Alternatives
This report
Date:
December 1966
Creator:
Baker, Kirby L.
Object Type:
Report
System:
The UNT Digital Library
Preparation and Properties of Plutonium Carbonitride.
None
Date:
January 1, 1966
Creator:
Guyton, J. L. & Thompson, M. A.
Object Type:
Report
System:
The UNT Digital Library
An Analog Computer Study of the Control Characteristics of the Medium Power Reactor Experiment System Including the Turbine-Generator.
None
Date:
January 1, 1966
Creator:
Burke, O. W.; Ditto, S. J. & Walker, C. S.
Object Type:
Report
System:
The UNT Digital Library
SNAP 19 capsule low Reynolds number force test
None
Date:
October 1, 1966
Creator:
Stouffer, C.G.
Object Type:
Report
System:
The UNT Digital Library
THERMAL CONDUCTIVITY AND ELECTRICAL RESISTIVITY OF ZIRCALOY-4.
None
Date:
January 1, 1966
Creator:
Feith, A.D.
Object Type:
Report
System:
The UNT Digital Library
FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE PHOEBUS 1-A EXPERIMENT.
None
Date:
January 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Design Study and Economic Evaluation of Head-End Reprocessing Facility Integral With an HTGR Power Plant
Preliminary designs and costs have been developed for nuclear fuel head-end reprocessing facilities integral with a large High-Temperature Gas-Cooled Reactor (HTGR) power plant.
Date:
January 1, 1966
Creator:
Stelling, H. E. & Steyer, K. G.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report for November 1966.
None
Date:
January 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Measurement of the K{sup 0}{sub S} - K{sup 0}{sub L} mass difference by the time dependence of strangeness
The magnitude of the K{sup 0}{sub S} - K{sup 0}{sub L} mass difference has been measured by monitoring the time dependence of the strangeness of neutral K's produced in hydrogen and deuterium in the LRL 25 '' hydrogen bubble chamber. The particles originate as K-bar{sup 0} in K{sup -} change-exchange scatters at .85 to 1.15 Bev/c; the signature for an S = -1 reaction is the production of a hyperon. Seventy- seven events were found, obtaining {Delta}{omega} = 0.50 =- 0.15, measured in units of inverse K{sup 0}{sub S} lifetime. This and two other recent measurements using the same method are consistent with one another and with measurements of {Delta}{omega} by other means. A combined ''world average'' of nine reasonably consistent measurements gives {Delta}{omega} = 0.60 +- 0.06.
Date:
April 1, 1966
Creator:
Camerini, U.; Cline, D.; English, J. B.; Fischbein, W.; Fry, W. F.; Gaidos, J. A. et al.
Object Type:
Article
System:
The UNT Digital Library
SCTI: Pressure Reducing Valve Body Failure.
None
Date:
January 1, 1966
Creator:
Wagner, R. K.
Object Type:
Report
System:
The UNT Digital Library
CONTROL CONCEPTS AND DIGITAL COMPUTER ANALYSIS OF THE MPRE FLUID SYSTEM.
None
Date:
January 1, 1966
Creator:
LaVerne, M.E.
Object Type:
Report
System:
The UNT Digital Library
Recovery of cesium, technetium, rhodium and palladium from stored waste supernates
The results of our assessment of the processing methods and costs for the recovery of cesium, techneium, rhodium, and palladium from aged waste supernates are presented. Guidelines for the assessment of costs are given. Cesium can be readily absorbed from alkaline waste supernates without prior treatment using Linde AW-500, a synthetic zolite. Technetium, present in the supernate as the pertechnetate anion, together with rhodium and palladium, probably present as anionic nitrite complexes, can be absorbed from untreated waste supernates using Dowex 1-X4 or similar anion resins. Although the behavior of cesium and technetium is reasonably well understood, the behavior of the anionic complex that accounts for the presence of rhodium and palladium in this strongly alkaline solution is not well understood. Further work is required before a process can be outlined for the clean separation of rhodium and palladium from the technetium-rhodium-palladium crude fraction sorbed on the anion resin. An assessment of capital and operating costs for the recovery of cesium only, technetium only, or both cesium and technetium are tabulated. No costs are shown for rhodium and palladium, since the technology for their separation is not sufficiently advanced. However, the incremental cost for their separation from technetium is expected …
Date:
June 22, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
A Modified Pyroelectric Sodium Fluoride Carrier Distillation Medthod For The Spectrographic Analysis Of Impurities In Plutonium
A modification of the pyroelectric sodium fluoride carrier distillation method for analysis of impurities in plutonium metal is described. The metal is dissolved. Plutonium is precipitated and treated with nitric acid. The slurry obtained is dried and ignited. The resultant low density oxide is mixed with sodium fluoride and pressed into a pellet for arcing. Cobalt is used as the internal standard for densitometric using visual comparisons against prepared standards. The procedural modifications improve reproducibility and sensitivity of most of the elements involved. (auth)
Date:
August 1, 1966
Creator:
Schreiber, G. A. & Barrick, C. W.
Object Type:
Article
System:
The UNT Digital Library
MPRE FUEL ELEMENTS: MANUFACTURE, INSPECTION, DRAWINGS, AND SPECIFICATIONS.
None
Date:
January 1, 1966
Creator:
Tolson, G.M.
Object Type:
Report
System:
The UNT Digital Library
ALTERNATE REACTOR CONCEPT DESIGN STUDY FOR THE FAST FLUX TEST FACILITY. FIXED SHIELD PLUG, VERTICAL CORE REACTOR CONCEPT.
None
Date:
January 1, 1966
Creator:
Duffy, J.G.; Hess, J.W.; Matte, J.; Mueller, R.E. & White, J.R.
Object Type:
Report
System:
The UNT Digital Library
Experimental Radiation Measurements in Conventional Structures: Part 1, Radiation Measurements in Two Two-Story and Three One-Story Typical Residential Structures Before and After Modification
Report discussing the methods, data, and analysis of results for "An experimental study designed to provide a basis for estimating protection against fallout radiation " (p. v) using one- and two-story structures with basements.
Date:
July 1966
Creator:
Burson, Z. G.
Object Type:
Report
System:
The UNT Digital Library
Aerial Radiological Monitoring System Part 4: Equipment and Procedures Through Fiscal Year 1966
From abstract: "This report describes the Aerial Radiological Measuring System (ARMS-II) operated by EG&G, Inc., for the Division of Biology and Medicine, U. S. Atomic Energy Commission."
Date:
March 1966
Creator:
Trundle, A. S., III & Story, E. J.
Object Type:
Report
System:
The UNT Digital Library
Proceedings of the Symposium on the Solidification and Long-Term Storage of Highly Radioactive Wastes: February 14-18, 1966, Richland, Washington
Symposium proceedings regarding long-term storage of highly radioactive wastes resulting from nuclear reactors.
Date:
November 1966
Creator:
Regan, W. H.
Object Type:
Report
System:
The UNT Digital Library
Aerothermodynamic analysis of the SNAP-27 fuel cask
An aerothermodynamic analysis of the SNAP-27 LEM fuel cask is presented for each of three mission aborts. Aerodynamic models for point mass and six degree-of-freedom trajectories are used, and the fuel cask heating rates and temperature responses are predicted for these trajectories. A survey of analytical and experimental studies of separated flow is related to the fuel cask, and a shock tunnel test program is outlined for further fuel cask analyses.
Date:
September 1, 1966
Creator:
McAlees, S., Jr.; Klett, R. D.; Pearce, B. E.; Larson, D. W.; Stephens, J. T. & Spahr, H. R.
Object Type:
Report
System:
The UNT Digital Library
WSEP 30-ton liquid transfer cask: Design criteria and performance tests
Shipment of radioactive wastes in shielded transfer casks is a continuing practice between the 300 Area and the 200 Areas. However, the Waste Solidification Engineering Prototypes (WSEP) located in 324 Building, 300 Area, require the transfer of significant quantities of radioactive wastes. Two new 30-ton casks are being placed in service to accommodate the increased number of shipments. The purpose of this report is to document the design criteria, tests and calculations performed on the casks and modifications to the original cask design to insure its safe use. The design criteria was developed in January 1963 by an ad hoc committee comprised of representatives of the Chemical Processing Department, Hanford Laboratories, and Construction Engineering and Utilities of General Electric Company. The various tests, calculations and modifications of the cask were conducted by the Chemistry Department of Pacific Northwest Laboratory.
Date:
March 30, 1966
Creator:
Cooley, C. R. & Spaeth, M. E.
Object Type:
Report
System:
The UNT Digital Library