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MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER. (open access)

MULTI-NODE SIMULATION OF THE FFTF INTERMEDIATE HEAT EXCHANGER.

None
Date: January 1, 1966
Creator: Gerhardstein, L.H.
System: The UNT Digital Library
DEEP SEA RADIOISOTOPE-FUELED THERMOELECTRIC GENERATOR POWER SUPPLY SYSTEM. SNAP-21B PROGRAM, PHASE I. Final Summary Report. (open access)

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.
System: The UNT Digital Library
Compensation for Victims of Crimes of Violence (open access)

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.
System: The UNT Digital Library
Precedents of the House of Representatives in Respects to Procedure for Censure or Expulsion, 1966 (open access)

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.
System: The UNT Digital Library
The Draft: Miscellaneous Materials Related to Selective Service and Some Proposed Alternatives (open access)

The Draft: Miscellaneous Materials Related to Selective Service and Some Proposed Alternatives

This report
Date: December 1966
Creator: Baker, Kirby L.
System: The UNT Digital Library
Preparation and Properties of Plutonium Carbonitride. (open access)

Preparation and Properties of Plutonium Carbonitride.

None
Date: January 1, 1966
Creator: Guyton, J. L. & Thompson, M. A.
System: The UNT Digital Library
An Analog Computer Study of the Control Characteristics of the Medium Power Reactor Experiment System Including the Turbine-Generator. (open access)

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.
System: The UNT Digital Library
SNAP 19 capsule low Reynolds number force test (open access)

SNAP 19 capsule low Reynolds number force test

None
Date: October 1, 1966
Creator: Stouffer, C.G.
System: The UNT Digital Library
THERMAL CONDUCTIVITY AND ELECTRICAL RESISTIVITY OF ZIRCALOY-4. (open access)

THERMAL CONDUCTIVITY AND ELECTRICAL RESISTIVITY OF ZIRCALOY-4.

None
Date: January 1, 1966
Creator: Feith, A.D.
System: The UNT Digital Library
FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE PHOEBUS 1-A EXPERIMENT. (open access)

FINAL REPORT OF OFF-SITE SURVEILLANCE FOR THE PHOEBUS 1-A EXPERIMENT.

None
Date: January 1, 1966
Creator: unknown
System: The UNT Digital Library
Design Study and Economic Evaluation of Head-End Reprocessing Facility Integral With an HTGR Power Plant (open access)

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.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report for November 1966. (open access)

Pacific Northwest Laboratory Monthly Activities Report for November 1966.

None
Date: January 1, 1966
Creator: unknown
System: The UNT Digital Library
SCTI: Pressure Reducing Valve Body Failure. (open access)

SCTI: Pressure Reducing Valve Body Failure.

None
Date: January 1, 1966
Creator: Wagner, R. K.
System: The UNT Digital Library
CONTROL CONCEPTS AND DIGITAL COMPUTER ANALYSIS OF THE MPRE FLUID SYSTEM. (open access)

CONTROL CONCEPTS AND DIGITAL COMPUTER ANALYSIS OF THE MPRE FLUID SYSTEM.

None
Date: January 1, 1966
Creator: LaVerne, M.E.
System: The UNT Digital Library
Recovery of cesium, technetium, rhodium and palladium from stored waste supernates (open access)

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
System: The UNT Digital Library
MPRE FUEL ELEMENTS: MANUFACTURE, INSPECTION, DRAWINGS, AND SPECIFICATIONS. (open access)

MPRE FUEL ELEMENTS: MANUFACTURE, INSPECTION, DRAWINGS, AND SPECIFICATIONS.

None
Date: January 1, 1966
Creator: Tolson, G.M.
System: The UNT Digital Library
ALTERNATE REACTOR CONCEPT DESIGN STUDY FOR THE FAST FLUX TEST FACILITY. FIXED SHIELD PLUG, VERTICAL CORE REACTOR CONCEPT. (open access)

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.
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 (open access)

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.
System: The UNT Digital Library
Aerial Radiological Monitoring System Part 4: Equipment and Procedures Through Fiscal Year 1966 (open access)

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.
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 (open access)

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.
System: The UNT Digital Library
Aerothermodynamic analysis of the SNAP-27 fuel cask (open access)

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.
System: The UNT Digital Library
WSEP 30-ton liquid transfer cask: Design criteria and performance tests (open access)

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.
System: The UNT Digital Library
FCC Reports, Second Series, Volume 2, December 15, 1965 to March 25, 1966 (open access)

FCC Reports, Second Series, Volume 2, December 15, 1965 to March 25, 1966

Biweekly, comprehensive compilation of decisions, reports, public notices, and other documents of the U.S. Federal Communications Commission.
Date: 1966-03~
Creator: United States. Federal Communications Commission.
System: The UNT Digital Library
Operation of a Reverse Osmosis Desalination Pilot Plant (open access)

Operation of a Reverse Osmosis Desalination Pilot Plant

Report demonstrating the technical feasibility of desalination by the Reverse Osmosis Process in a pilot plant cell containing 100 square feet of membrane area. A group of experimental tests are performed relating the desalination cell performance to the operating variables of brine flow rate, pressure, and brine concentration.
Date: 1966
Creator: Aerojet-General Corporation
System: The UNT Digital Library