UNT Libraries Government Documents Department - 50 Matching Results

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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

open access

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

open access

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

open access

Program Study Report Plutonium Fuel Cycle

From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."

Date: July 30, 1956

Creator: Albaugh, F. W. & Fryar, R. M.

Item Type: Report

open access

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

open access

N-Reactor Operational Safety Review

Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.

Date: August 19, 1963

Creator: Trumble, R. E.

Item Type: Report

open access

Standardization and Evaluation of Grain Size Test for Uranium Fuel

Report that "describes the selection of "standard fuel cores for calibrating an ultrasonic tester designated UT-2C" (p. 3) at Hanford Laboratories.

Date: July 1964

Creator: Spice, R. D.

Item Type: Report

open access

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

open access

Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.

Date: December 30, 1963

Item Type: Report

open access

Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964

Quarterly progress report on metallurgy research operations at Hanford Atomic Products Operation in Richland, Washington.

Date: April 27, 1965

Item Type: Report

open access

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

open access

Pyrophoricity of Uranium in Reactor Environments

Report discussing information relative to the pyrophoricity of uranium for the purpose of reactor core fire safety. The report includes physical and chemical properties of uranium.

Date: January 22, 1960

Creator: Zima, G. E.

Item Type: Report

open access

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Review of previous work is presented in addition to the results of recent studies concerning loss of primary coolant when the system is cold and pressurized and the problem of supplying adequate cooling following the injection of light water.

Date: November 15, 1960

Creator: Wittenbrock, N. G. & Muraoka, J.

Item Type: Report

open access

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis

Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.

Date: March 1962

Creator: Wittenbrock, N. G.

Item Type: Report

open access

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

open access

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

open access

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

open access

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

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

open access

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

open access

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

open access

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

open access

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

open access

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements

Report containing supplementary material for "Plutonium Recycle Critical Facility, Final Safeguards Analyses." This material expands upon previously supplied safety information and resolves previously unreviewed safety questions. Appendix begins on page A.1.

Date: October 1964

Creator: Swanberg, F.

Item Type: Report

UNT Libraries Government Documents Department - 50 Matching Results

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Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Final Design Report: DR-1 Gas Loop

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

Program Study Report Plutonium Fuel Cycle

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

N-Reactor Operational Safety Review

Standardization and Evaluation of Grain Size Test for Uranium Fuel

Magnetic Force Welding Sintered Aluminum Powder Materials

Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963

Quarterly Progress Report Metallurgy Research Operation: October, November, December, 1964

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

Pyrophoricity of Uranium in Reactor Environments

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 2, Consequences of a Primary Coolant Leak

Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis

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

Ultrasonic Resin Level Detector

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

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

Halogen Collector Test Program

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

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

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

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements