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  Partner: UNT Libraries Government Documents Department
 Serial/Series Title: HW (Series)
 Collection: Technical Report Archive and Image Library
6144-Channel Time-of-Flight Analyzer

6144-Channel Time-of-Flight Analyzer

Date: September 1964
Creator: Walker, R. A. & Russell, J. T.
Description: Report describing a 6144-channel analyzer designed and built for the purpose of analyzing time-of-flight during studies of slow neutron scattering at Hanford Laboratories. This includes descriptions of the analyzer, its logic and circuits, and its test mode.
Contributing Partner: UNT Libraries Government Documents Department
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept

Date: March 1, 1958
Creator: unknown
Description: From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Contributing Partner: UNT Libraries Government Documents Department
An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

An Alpha, Beta, Gamma Hand and Shoe Counter - Model 2

Date: June 2, 1958
Creator: Spear, W. G.
Description: Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.
Contributing Partner: UNT Libraries Government Documents Department
An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

An Alpha Scintillation Tester for Uranium Surface Contamination of N-Reactor Fuel

Date: July 1963
Creator: Jackson, C. N., Jr.
Description: Report that "describes a nondestructive tester and some of its applications in measuring 10 to 100 µg of uranium surface contamination on unirradiated, low enrichment, uranium fuel elements" (p. ii).
Contributing Partner: UNT Libraries Government Documents Department
Analog Computer Simulation of a Pulsed Extraction Column

Analog Computer Simulation of a Pulsed Extraction Column

Date: September 1964
Creator: Benham, R. D. & Wilburn, N. P.
Description: Report describing "computer techniques used in the simulation and parameter determination, how the data were prepared for inclusion in the computer simulation, (and) methods used in presenting the results" (p. 3-4).
Contributing Partner: UNT Libraries Government Documents Department
Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Analog Simulation of the Hanford N-Reactor Plant, Part 1: Description of the Overall Simulation Model

Date: September 1, 1964
Creator: Swanson, C. D.; Coughren, K. D.; Dionne, P. J. & Thieme, G. G.
Description: Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.
Contributing Partner: UNT Libraries Government Documents Department
An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Date: May 1, 1959
Creator: Rieck, H. G.
Description: From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
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
Automatic Sample Changer

Automatic Sample Changer

Date: January 3, 1957
Creator: Rankin, M. O.
Description: Automatic sample changer developed to increase the number of samples that can be handled daily.
Contributing Partner: UNT Libraries Government Documents Department
Beta-Gamma Dose Rates from U232 in U233

Beta-Gamma Dose Rates from U232 in U233

Date: April 1964
Creator: Owen, F. E.
Description: This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.
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
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
Construction Completion Report: CAI-816, 100-N Reactor Plant

Construction Completion Report: CAI-816, 100-N Reactor Plant

Date: October 15, 1964
Creator: Buckner, C. L.
Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Contributing Partner: UNT Libraries Government Documents Department
Conversion of UNH to UO3 : Terminal Report

Conversion of UNH to UO3 : Terminal Report

Date: January 10, 1951
Creator: Maness, R. G.
Description: Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.
Contributing Partner: UNT Libraries Government Documents Department
Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Corrosion Studies in Simulated N-Reactor Secondary System Water Environment

Date: May 1963
Creator: Larrick, A. P.
Description: Report containing the procedures and results of tests made to determine the corrosion resistance of materials in a simulation of Hanford Laboratories' N-Reactor secondary system water environment.
Contributing Partner: UNT Libraries Government Documents Department
Critical Mass Studies of Plutonium Solutions

Critical Mass Studies of Plutonium Solutions

Date: February 15, 1960
Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.
Description: Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.
Contributing Partner: UNT Libraries Government Documents Department
Description of Purex Plant Process

Description of Purex Plant Process

Date: May 19, 1959
Creator: Irish, E. R.
Description: Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Contributing Partner: UNT Libraries Government Documents Department
Description of the Thermal Hydraulics Laboratory at Hanford

Description of the Thermal Hydraulics Laboratory at Hanford

Date: June 2, 1960
Creator: Batch, J. M. & Toyoda, K. G.
Description: Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Contributing Partner: UNT Libraries Government Documents Department
Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks

Design and Installation of a High Precision Temperature and Intimate Contact Monitor for Experimental Vacuum Chucks

Date: May 15, 1958
Creator: Morrow, G. W.
Description: Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.
Contributing Partner: UNT Libraries Government Documents Department
The Detection of Earthquakes by Water-Level Recorders

The Detection of Earthquakes by Water-Level Recorders

Date: November 1955
Creator: McConiga, M. W.
Description: Detection of earthquakes by water-level recorders on water wells at Hanford Plant.
Contributing Partner: UNT Libraries Government Documents Department
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium

Date: October 1963
Creator: Wheelwright, E. J. (Earl J.) & Roberts, F. P.
Description: Report regarding "the development of a process suitable for large-scale separation of highly purified promethium from the trivalent fission product rare earth mixture" (p. 3).
Contributing Partner: UNT Libraries Government Documents Department
A Device for Recording Fuel Element Dimension on Punched Paper Tape

A Device for Recording Fuel Element Dimension on Punched Paper Tape

Date: December 1962
Creator: Driver, G. E.
Description: Report that "describes a system for translating the position of a strip-chart recorder potentiometer shaft into decimal digital form" (p. ii).
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
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI

Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI

Date: October 20, 1959
Creator: Moore, R. H.
Description: Report of data for the distributions of elements 90 through 96 between molten salt solutions of their chlorides and molten aluminum (or alloy) at 725 Celsius.
Contributing Partner: UNT Libraries Government Documents Department
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