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

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."

Date: March 1, 1958

Creator: Hanford Works

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

Experimental combination hand and shoe counter redesign as a compact, simplified, register readout instrument no larger than the present Five-Fold called Model 2.

Date: June 2, 1958

Creator: Spear, W. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

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."

Date: May 1, 1959

Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Beta-Gamma Dose Rates from U232 in U233

This report defines in detail the source of the dose rate of U233 and describes a method by which they may be predicted.

Date: April 1964

Creator: Owen, F. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

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.

Date: October 15, 1964

Creator: Buckner, C. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Conversion of UNH to UO3 : Terminal Report

Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.

Date: January 10, 1951

Creator: Maness, R. F. & Clagett, F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Critical Mass Studies of Plutonium Solutions

Chain reacting conditions for plutonium nitrate in water solution have been examined experimentally for a variety of sizes of spheres and cylinders.

Date: February 15, 1960

Creator: Kruesi, F. E.; Erkman, J. O. & Lanning, D. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Description of Purex Plant Process

Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.

Date: May 19, 1959

Creator: Irish, E. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.

Date: May 15, 1958

Creator: Morrow, G. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

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.

Date: October 20, 1959

Creator: Moore, R. H. & Lyon, W. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor

Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.

Date: June 17, 1954

Creator: Paul, R. S. & Wood, M. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.

Date: June 1961

Creator: Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Effect of Process Variables on Graphite Purity

Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.

Date: July 20, 1954

Creator: Riley, W. C. & Corners, A. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Comparison of experimentally determined relaxation lengths to the value calculated from the concrete composition.

Date: December 11, 1958

Creator: Wood, D. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).

Date: February 1961

Creator: Pessl, H. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.

Date: July 31, 1959

Creator: Knecht, R. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Factors Affecting Fluidization of Uranium Trioxide Powders

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.

Date: March 1, 1958

Creator: Johnson, B. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.

Date: September 1961

Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."

Date: April 16, 1951

Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.

Date: March 1961

Creator: Baars, R. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Final Design Report KAPL-120 High Pressure Recirculating Water Loop

Basic information on the design of the Knolls Atomic Power Laboratory (KAPL) -120 loop.

Date: January 15, 1956

Creator: Wade, G. E. & Berberet, J. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.

Date: June 26, 1959

Creator: Jackson, P. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Date: March 1, 1960

Creator: Arthur D. Little, Inc.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.

Date: June 1961

Creator: Muraoka, J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

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

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Beta-Gamma Dose Rates from U232 in U233

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

Conversion of UNH to UO3 : Terminal Report

Critical Mass Studies of Plutonium Solutions

Description of Purex Plant Process

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

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

Dual Channel Pulse Analyser and Count-Rate Meter for Gamma Spectrometer Monitor

Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor

Effect of Process Variables on Graphite Purity

The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Factors Affecting Fluidization of Uranium Trioxide Powders

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

Final Design Report: DR-1 Gas Loop

Final Design Report KAPL-120 High Pressure Recirculating Water Loop

Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

Halogen Collector Test Program

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility