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Temperature Transients Due to Density Changes on Changing Power Level in the HRT

Description: Changing the power level in the HRT leads to small average density changes in the high pressure system which produce noticeable changes in the nuclear average temperature. It is calculated that taking the reactor from zero power to 5Mw in one-half hour will lead to a temperature rise of about 0.7 degrees C, followed by a gradual fall over a two-hour period to about 1.3 degrees C below the temperature at zero power.
Date: April 6, 1961
Creator: Tobias, M.L. & Vondy, D.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Electroless Nickel Brazed Tube Bundles

Description: Two arrays of stainless steel tubes and ferrules which had been electroless nickel brazed were submitted for metallographic evaluation. These represented the first and second attempts of Ferrotherm of Cleveland to fabricate fuel bundles using the procedures outlined by Westinghouse Atomic Power Department for the Yankee Power Reactor.
Date: April 26, 1961
Creator: Crouse, R.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preparation and Specifications of Miniature Fermi Reactor Core B Fuel Specimens for Irradiation Testing

Description: The preparation of miniature plate specimens containing dispersions of 33.2 wt % UO2 in type 347 stainless steel for irradiation testing is described. These plates stimulate the prototype roll-bonded stainless steel clad composite plates intended for the Core B fuel element of the Enrico Fermi sodium-cooled reactor. The significant characteristics of the fabricated irradiation specimens are tabulated. The samples will be used to determine the irradation behavior of 33.2 wt % UO2 at temperatur… more
Date: April 21, 1961
Creator: Cherubini, J.H. & Williams, R.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Some Temperature Aspects of the HFIR Control Plate System

Description: This study examines the effects of water flow rate through the control region on local bulk water temperature and on control plate surface temperature, radial thermal expansion, and thermal stress. Flow rates of 1200, 800 and 400 gpm are considered for each of three control plate positions typical of startup, mid-cycle, and end-of-cycle. Based on the factors investigated in this study, the calculations indicate that a flow rate as low as 400 gpm may be reasonable.
Date: April 18, 1961
Creator: Haack, L.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Examinations of Pump Impellers From Sodium and Fused Salt Pump Endurance Tests

Description: Examinations of three Inconel pump impellers were made to establish the extent of cavitation damage and degree of carburization sustained during pump endurance tests. The pumps, two of which circulated fluoride salt and one sodium, had operated for the bulk of the test programs in the temperature range 1000-1250 deg F. Cavitation damage was manifested in each of the impellers by the formation of deep pits (in excess of 1/4-inch), the location of damaged areas varying with impeller geometry.
Date: April 10, 1961
Creator: DeVan, J.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Neutron Losses to Pa-233 in the Aqueous Homogenous Breeder Reactor

Description: Neutron losses to Pa-233 in the blanket of the AHBR were computed and compared for two cases: (1) concentration of Pa-233 is maintained uniform by continuous mixing, (2) batches of fertile material are shifted periodically from high- to low-flux regions of blanket. It was found that, if the fertile material is cycled through three radial positions in three days, the loss of neutrons to Pa-233 is no more than one per cent greater than if it is mixed continuously.
Date: April 26, 1961
Creator: Miller, J.W. & Alexander, L.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary MSRE Gamma Ray Source and Biological Shielding Survey

Description: The major gamma ray sources and some of the resultant biological shielding requirements have been evaluated at both full power operation and following shut down for the Molten Salt Reactor Experiment. The sources include gamma rays due to the fission events in the reactor and those associated with activation of materials. Shielding estimates were made for the reactor system cells and for some maintenance facilities.
Date: April 28, 1961
Creator: Vroom, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor

Description: Technical report covering the functions of the Oak Ridge reactor, difficulties encountered with cartridge failures in the Oak Ridge reactor, and possible solutions including the incorporation of leak detection systems into the design of the reactor.
Date: November 3, 1968
Creator: Chernick, J. & Kaplan, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Reactor Progress Report

Description: Technical report describing the building of safety devices and features for the Oak Ridge reactor by the Reactor Safeguard Committee of the Atomic Energy Commission. Outlines the difficulties encountered in detailed design and construction operations for the facility.
Date: October 1, 1948
Creator: Brookhaven National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Experimental and Theoretical Study of the Subcritical BNL Reactor

Description: Technical report outlining the theoretical study of the sub-critical BNL (Brookhaven National Laboratory) reactor, and a comparison of reactor performance with the purpose of presenting the experimental results of the experimental methods. Presents experimental results and and a detailed discussion of the experimental methods along with theoretical analysis and evaluation of the results.
Date: June 15, 1950
Creator: Cwernick, J.; Kaplan, I.; Kunstadter, J.; Sailor, V. & Williams, C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Preliminary Study of a Uranium - Bismuth Liquid Fuel Power Reactor L. F. R . 2

Description: Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.
Date: April 27, 1951
Creator: Gurinsky, D. H.; Kaplan, I.; Miles, F. T.; Williams, C. & Winsche, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Description: Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Jewish Speaker]

Description: Video footage from the WBAP-TV television station in Fort Worth, Texas, to accompany a news story.
Date: February 6, 1961
Duration: 2 minutes 23 seconds
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
open access

PM-1 Nuclear Power Plant Program: 3rd Quarterly Progress Report, September 1, 1959-November 30, 1959

Description: From abstract: The principal efforts are the furthering of the final design and preparation of specifications for some long-lead components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported.
Date: March 1960
Creator: Martin Company. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EGCR Graphite Permeability Tests: Results of Forced Flow Experiments on EGCR Moderator-Grade Graphite

Description: A knowledge of helium permeation rates through the various graphite components is necessary for EGCR design calculations. Helium-permeability and porosity were determined at room temperature for specimens from a typical EGCR moderator-grade graphite block.
Date: March 24, 1961
Creator: Ward, W.T. & Truitt, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Report of Reactor Science and Engineering Department; July 1 - September 30, 1951

Description: Technical report covering the classified tests on two types of nuclear reactors of the Department of Reactor Science and Engineering. Outlines tests on heat transfer and hydraulics, fabrication and corrosion studies on the normal water.
Date: 1951
Creator: Brookhaven National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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