34 Matching Results

Search Results

Results: 1 - 24 next
open access

The Applicability of Packed Glass Raschig Rings For Nuclear Safety In Large Vessels

Description: Simple calculations indicate that large diameter vessels packed with boron-containing glass raschig rings are applicable for storage of high concentration solutions of fissile material. Use of this means for storage of fissile solutions can result in appreciable savings. Advantages and disadvantages are discussed and tests are enumerated that must be made to confirm the applicability of glass raschig rings as a fixed poison.
Date: March 24, 1960
Creator: Nichols, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Bulk ThO2, a Reactor Material

Description: Thorium, a fertile material, is of interest to the Reactor Program in the production of U233. Thorium can be extracted and processed to a very pure bulk metal for fabrication into solid fertile elements. There are advantages, technical and economic, for using fabricated bulk thorium dioxide rather than the metal in some applications. It is the purpose of this paper to point out these advantages and to present briefly the technology related to fabrication, radiation damage and chemical processin… more
Date: May 24, 1956
Creator: Johnson, J. R. & Warde, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Calibration of Nude Ionization Gauges : Supplement No. 2 to ORNL-CF 61-5-109

Description: Whenever an ionization gauge without envelope (nude-type) is used on the same system with a conventional (tabulated) gauge different pressures are usually indicated by the type type of gauges. Three different models of nude Byart-Alpert type gauges have investigated: (1) Vactronic-N.I.G. (two), (2) Veeco RG-75 (denuded) and (3) Hughes-6578. Parallel calibrations of tublated RG075 gauges ere made in each case. Nude ionization gauges, when operated continuously for long periods of time in our tes… more
Date: November 24, 1961
Creator: Normand, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Demonstration of the Zirflex Process on Irradiated PWR Blanket Fuel

Description: Fifteen PWR blanket fuel specimens, varying in burnup from 80 to 1100 Mwd/T, were declad with boiling 6 M NH4F-1.0 M NH4NO3 before the UO2 core was dissolved in 10 M HNO3-uranium and plutonium losses to the decladding solution were less than 0.2% in nearly all runs.
Date: August 24, 1959
Creator: Gens, T. A.; West, G. A. & Ferris, L. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of Corrosion Products and Additives in Homogeneous Reactor Fuel III. Polarographic Determination of Iron(III)

Description: An ion-exchange -- polarographic method was developed for the determination of iron(III) in Homogeneous Reactor Fuels. Copper, which interferes, is removed from the fuel by plating it onto a cadmium coil. Iron is oxidized to iron(III) by potassium permanganate, and the iron(III) is separated from interfering metal ions by ion exchange on a Dowex 1 resin column that is in the sulfate form. The iron(III) in the effluent is determined polarographically in 0.5 M sodium citrate solution as supportin… more
Date: October 24, 1955
Creator: Horton, A. D.; Thomason, P. F. & Raaen, H. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of Trace Amounts of Sulfur in Fluoride Salts

Description: A method has been developed for the determination of total sulfur in fluoride salts using the methylene blue procedure. Reduction of sulfate to hydrogen sulfide is achieved through the use of a new reducing mixture consisting of stannous chloride dissolved in concentrated phosphoric acid. The new mixture is effective on microgram amounts of sulfate and offers a major advantage over the red phosphorous reducing mixtures in that larger samples may be taken for analysis. The procedure has been app… more
Date: June 24, 1957
Creator: Gilbert, T. W. & White, J. C.
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

Electronuclear Research Division Semiannual Progress Report For Period Ending March 20, 1955

Description: The ORNL 86-in. cyclotron is being modified to provide for deflection of the proton beam. It is expected that operation will be resumed late in the spring. Nuclear physics work was limited, for the most part, to interpretation of previously collected data and to making preparations for utilizing the deflected beam. It was found that for certain isotopes the production rates could be almost doubled by operating at a slightly reduced energy and a much larger current. With the use of the ORNL 63-i… more
Date: June 24, 1955
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimate of Hazard Produced by Accidental Release of Gaseous Fission Products from an ORR Fused Sale Capsule Experiment

Description: An accidental release of gaseous fission products from an ORR fused salt capsule, containing 26 mg. of U/sup 235/, was postulated and the resulting hazard estimated by calculating the maximum external and internal dose an individual could receive from exposure to the gaseous fission products and their decay products. Assuming all the contained gaseous fission products are released, the resulting external and internal dose, to organs other than the thyroid, arc insignificant. The dose to the thy… more
Date: April 24, 1959
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Estimated Gamma Radiation Levels at Access Holes in the HRT Shielding

Description: An estimate has been made of the gamma radiation levels at access holes in the HRT Shielding when the plugs have been removed to service or maintain the reactor. In every case the radiation level at the holes was greater than the maximum permissible exposure rate of 0.3 roentgens per week. The radiation through the holes can be attenuated to some extent by flooding the reactor cell up to the flange to be disconnected. However, shielding would still be required and it is more practical to provid… more
Date: January 24, 1957
Creator: Collins, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

An Evaluation of the Present Status of Swirl-Flow Heat Transfer

Description: Available swirl-flow data for pressure drop, heat transfer under both nonboiling and boiling conditions, and burnout have been collected and compared on common bases. Though different sets of data are in some disagreement, semiquantitative overall trends are discernible. It is shown that swirl flow allows attainment of greater heat-transfer rates under a variety of conditions, both without boiling and at burnout, than are characteristic of axial flow at the same pumping power.
Date: April 24, 1961
Creator: Gambill, W.R. & Bundy, R.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Feasibility Tests - Electrolytic Dissolution of Perforated Zircaloy-2 Screens

Description: The intent of the program described in this report was to develop a method of removal of the core screens of the HRT. The purpose of the test was to determine first, if perforated zircaloy-2 screen samples could be electrolytically dissolved in small bench tests, under controlled conditions, and then to translate this experience to the development of proper equipment to perform a full-scale mockup demonstration of practicability.
Date: November 24, 1959
Creator: Draper, B. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final Cycle Plutonium Recovery by Amine Extraction

Description: The flowsheet visualized from development work thus far for final plutonium recovery and purification will accept as feed a Purex partition stream without feed adjustment beyond the usual reoxidation. Extraction with trilaurylamine at approximately 0.3M appears suitable for 20 to 60 g Pu/liter product from 0.5 to 2 g Pu/liter feed. Scrubbing with either ((2 M or))2 M HNO/ sub 3/ is possible. Acetic acid is at present the first choice for stripping agent, with oil-soluble and aqueous-soluble org… more
Date: May 24, 1961
Creator: Coleman, C. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Forced Convection Heat Transfer to Slurries in Tubes

Description: An analysis has been made in order to predict the heat transfer coeffect for slurries flowing in tubes. For the laminar flow of a slurry the coefficient of heat transfer from the tube wall to the slurry may be predicted by the following equations: [equation]. Heat loss data for the turbulent flow of slurries indicated that they behave as true fluids with a constant "turbulent" viscosity which may be determined experimentally. If this behavior is real rather than apparent the heat transfer coeff… more
Date: November 24, 1952
Creator: Bailey, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fuel Cycle Costs in a Graphite Moderated Slightly Enriched Fused Salt Reactor

Description: A fuel cycle economic study has been made for a 315 Mwe graphite- moderated slightly enriched fused-salt reactor. Fuel cycle costs in the order of 3.3 mills/kwh were calculated for the throw-away cycle. Recovery of the uranium and plutonium at the end of the cycle reduces the fuel cycle costs to approximately 1.6 mill/kwh. Changes in the waste storage cost and reprocessing cost have a relatively minor effect on fuel cycle costs.
Date: February 24, 1959
Creator: Guthrie, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-Thermal-Conductivity Fin Material for Radiators

Description: This report is the result of a study to develop heat-resistant fin materials possessing a high thermal conductivity for air radiators. Since an economical and commercially feasible product was desired, the investigation was restricted primarily to a study of electroplated copper, clad copper, and copper alloys. Sheet material 0.008 to 0.010 in. thick was evaluated for fabricability and for metallurgical stability and thermal conductivity at 1500°F. From the results of the rests it was concluded… more
Date: January 24, 1957
Creator: Inouye, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Experiment Quarterly Progress Report [for] Period Ending August 31, 1950

Description: Technical report containing the detailed design of the equipment within the reactor shield, reviewed in 1950. Contains various summaries on engineering design and development, reactor physics, chemical studies, and corrosion.
Date: October 24, 1950
Creator: Winters, C. E.; Gall, W. R.; Graham, C. B.; Quarles, L. R.; Stein, J. M.; Clewett, G. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lecture Notes on Reactor Controls

Description: This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R… more
Date: June 24, 1959
Creator: Walker, C. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Minutes of Third Meeting of Reactor Decontamination Information Exchange Group at ORNL, June 1-2, 1961

Description: The third semiannual meeting of the AEC-sponsored Reactor Decontamination Information Exchange Group was help at ORNL during June 1 and 2 1961. Nine reactor installations including Chalk River, were represented by personnel from their decontamination research teams. Although the meeting was a series of informal round-table discussion, with wide publication not contemplated, each member subsequently summarized the decontamination research at this installation during the last six month for public… more
Date: July 24, 1961
Creator: Meservey, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MTR, Relative Volumes of Aluminum , Water , Beryllium and Air in Core and Reflector

Description: A detailed study of MTR drawings has been made to determine the aluminum to water ratio in the core and the volume of water, aluminum, beryllium and air in the reflector. Also effects of certain changes on the aluminum to water ratio in the core were calculated.
Date: July 24, 1952
Creator: Gall, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Merchant Ship Reactor Final Safeguards Report, Volume 6: Environmental Analysis OF NS "Savannah" Operation at Camden

Description: "An analysis is presented of the accidental release of activity following the operation of the NS "Savannah" at the New York Shipbuilding Corporation docks in Camden, New Jersey. Although a number of accidents are considered, the report is primarily concerned with the environmental activity levels and subsequent exposures which would result from the "maximum credible accident" (p. v).
Date: January 24, 1961
Creator: Cottrell, W. B.; Parker, F. L.; Mann, L. A. & Schmidt, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen