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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: TID
 Collection: Technical Report Archive and Image Library
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions

Date: October 1963
Creator: Spear, W. G.
Description: Report containing a method for beta-gamma counting of hands, shoes, and clothing via an instrument that employs scintillation detectors and solid-state circuits.
Contributing Partner: UNT Libraries Government Documents Department
In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

In-Reactor Monitoring of Zircaloy-2 Plutonium Recycle Test Reactor Pressure Tubes: Part 2, May and June, 1962

Date: August 1962
Creator: Doman, D. R. & Pankaskie, P. J.
Description: Report containing the results of a two year program wherein the 85 zircaloy-2 pressure tubes in Hanford Laboratories' Plutonium Recycle Test Reactor (PRTR) were monitored. Experimental procedures and results are described.
Contributing Partner: UNT Libraries Government Documents Department
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements

Date: August 1962
Creator: Hanthorn, H. E.
Description: Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Contributing Partner: UNT Libraries Government Documents Department
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Date: April 1963
Creator: Rieck, H. G. 1922-
Description: Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Contributing Partner: UNT Libraries Government Documents Department
Fuel Core Tester - UT-2

Fuel Core Tester - UT-2

Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Contributing Partner: UNT Libraries Government Documents Department
Dissolution of Power Reactor Fuel Cores

Dissolution of Power Reactor Fuel Cores

Date: August 26, 1960
Creator: Blaine, H. T.
Description: Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Contributing Partner: UNT Libraries Government Documents Department
Hanford Controlled Potential Coulometer

Hanford Controlled Potential Coulometer

Date: July 11, 1960
Creator: Connally, R. E. & Scott, F. A.
Description: Report describing the Hanford Laboratory controlled potential coulometer. This includes the theory behind the coulometer, details of its circuitry, and performance tests. Appendix begins on page 23.
Contributing Partner: UNT Libraries Government Documents Department
Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962

Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience: August 1960 Through November 1962

Date: March 1963
Creator: Scott, P. A.
Description: Report documenting experience gained by operating the spare PRTR Primary Process Pump. This includes descriptions of equipment used, testing procedures, and operating history.
Contributing Partner: UNT Libraries Government Documents Department
Hanford Summary Report for the Hanford Plutonium Critical Mass Laboratory

Hanford Summary Report for the Hanford Plutonium Critical Mass Laboratory

Date: August 1, 1960
Creator: Reardon, W. A.; Clayton, E. D.; Brown, C. L.; Masterson, R. H.; Powell, T. J.; Richey, C. R. et al.
Description: Report that summarizes the potential hazards of the Hanford Critical Mass Laboratory and presents operation procedures which will limit the probability of a nuclear accident. The report also outlines the planned experimental program, descriptions of the facility, and the administration of nuclear safety in the laboratory.
Contributing Partner: UNT Libraries Government Documents Department
The Thermal Hydraulics Laboratory at Hanford

The Thermal Hydraulics Laboratory at Hanford

Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Description: Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Contributing Partner: UNT Libraries Government Documents Department
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Date: August 12, 1960
Creator: Wilburn, N. P.
Description: Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Contributing Partner: UNT Libraries Government Documents Department
The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

The Radiation Leakage Survey of the Shield of the Nuclear Ship Savannah

Date: August 29, 1962
Creator: Blizard, E. P.; Blosser, T. V. & Freeston, R. M.
Description: Report containing a survey of the radiation from the nuclear ship Savannah in order to determine the dose rate for people aboard.
Contributing Partner: UNT Libraries Government Documents Department
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Date: October 1969
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Description: Report documenting the ongoing research and development of the Oak Ridge National Laboratory's Chemical Technology Division.
Contributing Partner: UNT Libraries Government Documents Department
Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Low-Radioactivity-Level Waste Treatment. Part II: Pilot Plant Demonstration of the Removal of Activity from Low-Level Process Wastes by a Scavenging-Precipitation Ion-Exchange Process

Date: May 27, 1963
Creator: Brooksbank, R. E.; Browder, F. N.; Holcomb, R. R. & Whitson, W. R.
Description: Report documenting the process of decontaminating low-activity fuel waste water via the Scavenging-Precipitation Ion-Exchange process. This includes analyses of the costs of the process as well as a description of the operation of the pilot plant.
Contributing Partner: UNT Libraries Government Documents Department
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Date: September 21, 1962
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
Description: Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Contributing Partner: UNT Libraries Government Documents Department
Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Specifications and Procedures Used in Manufacturing U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor

Date: October 21, 1963
Creator: Kucera, W. J.; Leitten, C. F., Jr. & Beaver, R. J.
Description: Report containing the description and design of U₃O₈-Aluminum Dispersion Fuel Elements for Core I of the Puerto Rico Research Reactor. Topics include the requirements of core materials, materials specifications, manufacturing procedures, and shipping preparation.
Contributing Partner: UNT Libraries Government Documents Department
Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Evaluation of a Reduced Pressure Backflow Preventer Using Activation Analysis

Date: 1963-01-uu
Creator: Baird, Justus N., Jr.; Sanford, W. R. & Cristy, G. A.
Description: Report containing tests performed to evaluate a reduced pressure backflow preventer. This includes preliminary tests, resulting improvements, and final rests. Appendices begin on page 23.
Contributing Partner: UNT Libraries Government Documents Department
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Date: April 4, 1963
Creator: Oak Ridge National Laboratory
Description: Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Contributing Partner: UNT Libraries Government Documents Department
Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Date: 1964
Creator: Donnelly, R. G.; Thurber, W. C. & Slaughter, G. M.
Description: Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57.
Contributing Partner: UNT Libraries Government Documents Department
The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study

Date: 1963
Creator: unknown
Description: Report documenting the design of the Oak Ridge National Laboratory Gas-Cooled Clad-Fuel Reactor Power Plant. This includes design criteria and parameters, costs, and descriptions of systems.
Contributing Partner: UNT Libraries Government Documents Department
Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Procedures for Fabricating Aluminum-Base ATR Fuel Elements

Date: June 1964
Creator: Beaver, R. J.; Patriarca, P. & Adamson, G. M.
Description: Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Contributing Partner: UNT Libraries Government Documents Department
Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963

Maritime Reactor Project Annual Progress Report for Period Ending November 30, 1963

Date: March 1965
Creator: McCurdy, H. C.
Description: Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1963 are presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956

Instrumentation and Controls Division Semiannual Progress Report for Period Ending July 31, 1956

Date: February 25, 1957
Creator: Borkowski, C. J.
Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Instrumentation and Controls Division. Descriptions of progress and studies conducted are presented. This report includes illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Microscopic and Autoradiographic Studies of Distribution of Uranium in the Rat Kidney

Date: February 1965
Creator: Jones, Edith Seymour
Description: Report issued by the Oak Ridge National Laboratory discussing studies conducted on uranium retention in rat kidneys. Methods, equipment, and results of the studies are presented. This report includes tables, illustrations, and photographs.
Contributing Partner: UNT Libraries Government Documents Department
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