55 Matching Results

Search Results

Results: 1 - 24 next
open access

Rotating Machinery for Gas-Cooled Reactor Application

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Analytical Chemistry in Nuclear Reactor Technology: 1961

Description: "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.
Partner: UNT Libraries Government Documents Department
open access

Radiation Safety and Control Training Manual

Description: 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
Partner: UNT Libraries Government Documents Department
open access

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants

Description: Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.
Date: June 30, 1962
Creator: Chittenden, W. A. & Hoveke, G. F.
Partner: UNT Libraries Government Documents Department
open access

1000-MWe LMFBR Follow-On Study, Task I Report: Volume 1

Description: From introduction: "The objective of this study is to provide information that will assist the Atomic Energy Commission in furthering the National Liquid Metal Fast Breeder Reactor (LMFBR) Program. We plan to accomplish this end, in part, by extending the original studies to include system and component design and parametric evaluations of the nuclear steam supply system and its related systems and subsystems based on an estimation of the state of technology in 1980."
Date: June 1967
Creator: Goulding, B. J.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

VBWR Stability Test Report

Description: Analysis of the stability of boiling water reactors.
Date: June 1963
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
open access

Engineering Test Reactor Critical Facility Control System Manual

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

STEP Project Quarterly Technical Report: January-June 1964

Description: Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.
Date: June 1965
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Partner: UNT Libraries Government Documents Department
open access

In-Pile Radiation Corrosion Experiments with Zirconium, Titanium, and Steel Alloys in 0.17 m UO2SO4 Solutions at 280°C

Description: In-pile loop experiments L-2-15 and L-4-16 were two of a series designed to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various conditions of radiation intensities, temperatures, solution compositions, and velocity flow past specimens.
Date: June 10, 1963
Creator: Jenks, G. H.
Partner: UNT Libraries Government Documents Department
open access

Irradiation Effects in the EGCR Fuel

Description: From foreword: "This is a documentation of the experiments performed and the data accumulated during the early period of the Experimental Gas-Cooled Reactor (EGCR) fuel element design."
Date: June 1965
Creator: Baumann, C. D.
Partner: UNT Libraries Government Documents Department
open access

Post-Test Physical, Chemical and Metallurgical Analysis of SNAPTRAN-3 Fuel

Description: The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.
Date: June 1965
Creator: Fletcher, R. D.
Partner: UNT Libraries Government Documents Department
open access

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

Description: 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.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen