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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

open access

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

open access

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

open access

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

open access

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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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

open access

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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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

open access

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

open access

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

open access

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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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

open access

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

open access

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

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

Partner: UNT Libraries Government Documents Department

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

Partner: UNT Libraries Government Documents Department

open access

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

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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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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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

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

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

Partner: UNT Libraries Government Documents Department

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

Partner: UNT Libraries Government Documents Department

open access

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

39 Matching Results

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Final Design Report KAPL-120 High Pressure Recirculating Water Loop

Joint Design for Making Root Pass Welds without Filler Material

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

A Martensitic Reaction for Uranium

Plating Thickness Tester

Factors Affecting Fluidization of Uranium Trioxide Powders

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

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

The Effect of Temperature on the Neutron Attenuation of Magnetite Concrete

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

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

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

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

Ultrasonic Resin Level Detector

Pyrophoricity of Uranium in Reactor Environments

Critical Mass Studies of Plutonium Solutions

Halogen Collector Test Program

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

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

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

Final Design Report: DR-1 Gas Loop

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

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements