55 Matching Results

Search Results

open access

Lawrence Radiation Laboratory Chemistry Division Quarterly Report: March - May 1953

Quarterly report of the Chemistry Division at the University of California Radiation Laboratory providing updates for each department about current findings and ongoing research.

Date: June 25, 1953

Creator: Lawrence Radiation Laboratory. Chemistry Division.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Liquid Metal Reactor Experiment Research and Development Program, June 1957

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment. This includes engineering information concerning the design, construction, and operation of the experiment.

Date: June 1957

Creator: Babcock & Wilcox Company

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

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

Plutonium Recycle Test Reactor Preliminary Safeguards Analysis

Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.

Date: June 5, 1958

Creator: Wittenbrock, N. G.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

HRP Radiation Corrosion Studies: In-Pile Loop L-4-11

Report issued by the Oak Ridge National Laboratory discussing radiation corrosion studies. As stated in the introduction, "the purpose of this experiment was to compare the performance of a large number of materials under similar irradiation and exposure conditions" (p. 1). This report includes tables, illustrations, and photographs.

Date: June 27, 1958

Creator: McWherter, J. R. & Baker, J. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.

Date: June 1959

Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Physics Division Annual Progress Report, March 10, 1959

Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.

Date: June 10, 1959

Creator: Oak Ridge National Laboratory. Physics Division.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Scintillation spectrometry is used to measure the gamma activity from uranium for determining lung burden in the human body.

Date: June 23, 1959

Creator: Cofield, Rogers E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.

Date: June 24, 1959

Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

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

Molten-Salt Reactor Program Quarterly Progress Report: April 1959

Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.

Date: June 26, 1959

Creator: Oak Ridge National Laboratory

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959

From abstract: This paper discusses the use of high flux reactors to remove a number of deficiencies in the knowledge of the interaction of neutrons with matter.

Date: June 1960

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Evaluation and Design Heavy Water Moderated Power Reactor Plants

From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.

Date: June 30, 1960

Item Type: Report

Partner: UNT Libraries Government Documents Department

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

Partner: UNT Libraries Government Documents Department

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

Partner: UNT Libraries Government Documents Department

open access

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.

Date: June 1961

Creator: Todd, R. H.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Radiation Safety and Control Training Manual

Introduction: The Laboratory follows the recommendations of the National Committee on Radiation Protection concerning permissible exposure limits for those working with radiation. A system of controls and regulations has been established which should ensure that no person at the Laboratory will receive more than the permissible exposure. This manual is intended to provide the minimum background necessary for intelligent cooperation with the regulations.

Date: June 1, 1961

Creator: Oak Ridge National Laboratory

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Engineering Test Reactor Critical Facility Control System Manual

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).

Date: June 23, 1961

Creator: Meichle, F. A.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.

Date: June 27, 1961

Creator: Oak Ridge National Laboratory

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.

Date: June 30, 1961

Creator: Chittenden, W. A. & Hoveke, G. F.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Analytical Chemistry in Nuclear Reactor Technology: 1961

"An Automated Spectrograph has been developed for the analyses of beryllium contained on filter paper discs. With this instrument, unattended analyses can be carried out on a number of samples following simple sample preparation. Filter paper discs representing beryllium in the atmosphere as well as those used for evaluating surface contamination are accommodated. Included in the uniting are an automatic electrode changer, analytical gap servo control, spectrograph, signal detector, and compute… more

Date: June 1962

Creator: Susano, C. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Rotating Machinery for Gas-Cooled Reactor Application

From foreword: Representatives from various organizations met to discuss progress in the development of rotating machinery for gas-cooled reactors. The equipment covered included main blowers, shaft seals, gas turbines, gas bearing compressors, and other types of special compressors for reactor or experimental applications.

Date: June 1962

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia

From abstract: "The Darex process developed for the recovery of uranium from stainless steel-containing reactor fuels consists of three steps: (1) dissolution of the fuel material in dilute aqua regia, (2) removal of chloride from the solution to prevent corrosion of downstream stainless steel process equipment, and (3) adjustment of the nitrate solution to solvent extraction feed conditions."

Date: June 7, 1962

Creator: Kitts, F. G. & Clark, W. E.

Item Type: Report

Partner: UNT Libraries Government Documents Department

55 Matching Results

Search Results

Add Filters

Applied Filters

Lawrence Radiation Laboratory Chemistry Division Quarterly Report: March - May 1953

Liquid Metal Reactor Experiment Research and Development Program, June 1957

A Martensitic Reaction for Uranium

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

Plutonium Recycle Test Reactor Preliminary Safeguards Analysis

HRP Radiation Corrosion Studies: In-Pile Loop L-4-11

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Physics Division Annual Progress Report, March 10, 1959

In Vivo Gamma Counting Method of Determining Uranium Lung Burden in Humans

Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958

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

Molten-Salt Reactor Program Quarterly Progress Report: April 1959

Symposium on High Flux Materials Testing Reactors: Held in Brussels, Belgium. September 21-26, 1959

Evaluation and Design Heavy Water Moderated Power Reactor Plants

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

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

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

Radiation Safety and Control Training Manual

Engineering Test Reactor Critical Facility Control System Manual

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Analytical Chemistry in Nuclear Reactor Technology: 1961

Rotating Machinery for Gas-Cooled Reactor Application

Darex Process: Processing of Stainless Steel-Containing Reactor Fuels with Dilute Aqua Regia