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Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.

Date: February 1962

Creator: Anderson, J. K. & Winegardner, W. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

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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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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A Martensitic Reaction for Uranium

Series of isothermal transformation studies for improvement in fabrication and reactor performance of uranium fuel elements.

Date: June 25, 1957

Creator: Bement, A. L. & Wallace, W. P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.

Date: December 15, 1958

Creator: Brauer, F. P. & Burley, Helen H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Plating Thickness Tester

An electromagnetic eddy current instrument is described that is capable of measuring copper and nickel plating 1 to 8 mils thick plated on bismuth mandrils of various sizes and shapes.

Date: November 15, 1957

Creator: Fitch, C. E., Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).

Date: March 1961

Creator: Freshley, M. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.

Date: May 1963

Creator: Hanthorn, H. E.

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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Ultrasonic Resin Level Detector

This report describes the development of an ultrasonic instrument for resin level measurements in an ion exchange column.

Date: January 15, 1960

Creator: Hunter, D. O. & Pleasance, C. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium

Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.

Date: April 8, 1957

Creator: Irish, E. R. & Reas, W. H.

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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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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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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Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.

Date: April 1961

Creator: Koler, R. K.

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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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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Joint Design for Making Root Pass Welds without Filler Material

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.

Date: July 9, 1956

Creator: Lemon, L. C. & Smith, W. R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Specifications including detail dimension, materials, fabrication steps, acceptance criteria, and final assembly steps for the swaged uranium dioxide, 19-rod cluster Plutonium Recycle Test Reactor fuel element.

Date: March 15, 1960

Creator: Millhollen, M. K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Magnetic Force Welding Sintered Aluminum Powder Materials

Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.

Date: March 1962

Creator: Mills, L. E.

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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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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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

open access

Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.

Date: May 20, 1964

Creator: Nelson, R. William

Item Type: Report

Partner: UNT Libraries Government Documents Department

39 Matching Results

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Plutonium Recycle Critical Facility: Final Safeguards Analysis

Halogen Collector Test Program

Final Design Report: DR-1 Gas Loop

A Martensitic Reaction for Uranium

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Plating Thickness Tester

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis

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

Ultrasonic Resin Level Detector

The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium

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

Factors Affecting Fluidization of Uranium Trioxide Powders

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Critical Mass Studies of Plutonium Solutions

Joint Design for Making Root Pass Welds without Filler Material

Specifications for Swaged UO2 19-Rod Cluster, PRTR Fuel Element Mark 1

Magnetic Force Welding Sintered Aluminum Powder Materials

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

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

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

Steady Darcian Transport of Fluids in Heterogeneous Partially Saturated Porous Media: Part 2, the Computer Program