686 Matching Results

Search Results

Results: 1 - 24 next
open access

Southwest Retort, Volume 11, Number 5, January 1959

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: January 1959
Creator: American Chemical Society. Dallas/Fort Worth Section.
Item Type: Refine your search to only Journal/Magazine/Newsletter
Partner: UNT Libraries
open access

The Injection Casting of Plutonium

Description: Plutonium metal can be injected into cold metal molds to form castings with thin walls. The operation is performed in a vacuum chamber, using an inert gas as the injecting medium. Sound pieces free of gas cavities can be made using either pure or delta-stabilized plutonium. This report describes the equipment and techniques used to cast a typical thin section piece in the form of a 6 in. diameter, 45' cone.
Date: January 1959
Creator: Anderson, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Aging of Al-Li Alloys - Part I

Description: Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) … more
Date: January 1959
Creator: Angerman, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NEUTRON-FLUX MEASUREMENTS IN A CONCENTRIC-CYLINDER FUEL ELEMENT

Description: Neutron-flux measurements in a concentric-cylinder fuel element were made in a gas-cooled in-pile loop operated adjacent to the core of the BRR. The fuel element comprised four concentric fuel cylinders. Each fuel annulus (outside diameters- 1.248 1.018, 0.810 and 0.590 in.) consisted of a 0.031-in.- thick core of UO/sub 2/ dispersed in type 347 stainless steel and clad on each side with 0.007 in. of typee 318 stainless steel. The element was 24 in. long and the total uranium-235 content was ap… more
Date: January 29, 1959
Creator: Anno, J.N.; Fairand, B.P. & Chastain, J.W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REQUIREMENTS FOR RAW MATERIALS IN AN EXPANDING NUCLEAR POWER ECONOMY

Description: The need for breeding does not appear to be highly cost for a moderately optimistic expanding nuclear power economy between 1960 and 2000. Since the expansion rate of the US nuclear economy is assumed to be high at least 2/3 of the U-235 recovered from natural uranium is used to supply reactor inventory. It is the remaining 1/3 of the available U-235 that can be saved by breeder breeders or a breeder and converter are the doubling time and a parameter expressing the total fissile inventory per … more
Date: January 20, 1959
Creator: Arnold, E.D. & Ullmann, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CIVILIAN POWER REACTOR PROGRAM. PART III. CORE-PARAMETER STUDIES FOR SELECTED REACTOR TYPES

Description: A report is presented to provide a tool for evaluating the relative economic incentives for changing reactor core parameters. The cost relations are shown in terms of differential cost in lieu of total cost. A total cost for each reactor described is included so that power costs for a specified set of parameters can be obtained. A description is also included concerning 5 reactor types considered along with a discussion of the effects on power costs of varying the significant core parameters. A… more
Date: January 1, 1959
Creator: Atomic Energy Commission, Washington, D.C. & Jackson and Moreland, Inc., Boston
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FIELD STUDY OF THE AgPO$sub 3$ GLASS PERSONNEL DOSIMETER (U.S. NAVY DT-60)

Description: >The U. S. Navy DT-60 dosimeter was evaluated under field type conditions as to its reproducibility and accuracy of gamma x-ray, thermal and fast neutron and mixed radiation responses. Gamma and x-ray responses from 25 to 600 rads at energies in oxcess of 200 kev were found to be accurate within 20% in 92% of 160 dosimeters examined. Because the DT-60 was found to have no detectable fast neutron response, effort was directed toward exaggerating the thermal neutron response to approximate the to… more
Date: January 1, 1959
Creator: Ballinger, E.R. & Harris, P.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A PRELIMINARY STUDY OF THE NUCLEAR STABILITY OF FLUIDIZED BED REACTORS

Description: A preliminary study was made of the nuclear stability of reactors in which particles containing U/sup 233/ and Th/sup 232/ are fluidized by liquid water. D/sub 2/O moderated reactors were found to be least sensitive to changes in bed height at thorium concentrations in the range 80 to 120 g/liter, H/sub 2/O reactors in the rarnge 1500 io 2400 g Th/ liter, and mixed H/sub 2/O-D/sub 2/O reactors at thorium concentrations between those for pure moderators. A reactor operated at the thorium concent… more
Date: January 12, 1959
Creator: Benumof, R. & Rosenthal, M.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Studies on Large Area Sub-Fabric Burns: The Effect of an Air Space Between a Two Layer System

Description: It is well known that protection against radiant energy burns afforded by fabrics may be increased by creating an air space between the fabric and the underlying skin. Earlier work in this laboratory has also shown that if one layer of fabric is in contact with skin, protection of a two layer fabric system increases progressively as the space between the fabrics changes from two to five millimeters. With the magnesium source, large area sub-fabric burns were produced to determine the cffects of… more
Date: January 14, 1959
Creator: Berkley, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Solid State Division Quarterly Progress Report: August 1952

Description: This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date: January 30, 1959
Creator: Billington, D. S. (Douglas S.) & Howe, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

NUCLEAR BATTERY--THERMOCOUPLE TYPE. Quarterly Progress Report No. 7 for July 1, 1958 to September 30, 1958

Description: Calculations were made to estimate the minimum amounts of isotopes, as the element or appropriate compound, which had sufficient power output to raise their temperatures to 200 and 2300 deg C. Construction has begun on a second battery. (For preceding period see MLMCF-58-7-19). (auth)
Date: January 1, 1959
Creator: Blanke, B.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Variable goal equations for enriched and natural I and E material at the C and K Reactors

Description: We have previously transmitted interim recommendations of goal exposure plans for enriched I&E material at the C and K reactors and for natural I&E material at the K Reactors. We indicated in the references that corrections for changes in inlet temperature would be forthcoming. The purpose of this letter is to transmit revised goal exposure equations.
Date: January 20, 1959
Creator: Bloomstrand, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

RESULTS OF THERMAL CYCLING STRESS CORROSION TESTS OF TYPE-347 STAINLESS STEEL IN 500 F pH 10-11 LITHIUM HYDROXIDE

Description: The results of a one-month thermal cycling corrosion test of three stressed T-347 stainless steel bolts exposed to 500 deg F pH 10 to 11 lithium hydroxide are described. Tests were made to evaluate corrosion of stressed T-347 and T-304 stainless steel under conditions of water leakage to the atmosphere. (W.D.M.)
Date: January 1, 1959
Creator: Borrmann, G.H. & Galonian, G.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Increased pumping capacity at 181-C scope and justification

Description: The purpose of this report is to provide scope and justification for the installation of two new 16,500 gpm, 150-foot head pumps in the 181-C building in order to furnish sufficient additional water to increase production at 105-B and to supply the entire normal export demand from B Area. A minimum of 11,000 gpm will be required to be transferred from the 183-C reservoir to the 183-B clearwell via the cross-tie line during the adverse turbidity period when the I&E program is in effect at 105-B.… more
Date: January 7, 1959
Creator: Brinkman, L. B. & Blanchette, V. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE

Description: It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 300… more
Date: January 15, 1959
Creator: Brown, K. E.; Jessen, F. W. & Gloyna, E. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Waste Treatment and Disposal Problems of the Future Nuclear Power Industry

Description: The elements of waste treatment and disposal are assessed which are expected to become important in the development of the nuclear power industry of the future. Growth of the nuclear power economy is considered along with composition and quantities of anticipated waste. In addition, the economic implications of waste disposal are considered. It is concluded that research should be concentrated on decontaminating off-gases and on conversion of wastes to a more suitable form than liquid for stora… more
Date: January 28, 1959
Creator: Bruce, F.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

F0020-AN IBM-704 THERMAL TRANSIENT ANALYSIS CODE

Description: An IBM-704 thermal transient analysis code, designated F0020 was developed to reduce transient test data for a single vertical, rectangular coolant channel. Modes of heat transfer to water at 2000 psia covered by this code include forced convection (turbulent flow), nucleate boiling, departure from nucleate boiling, partial film boiling, and film boiling. The code will accommodate a plate mesh, and associated heat generation weighting factors, of a maximum of 50 axial and 10 radial nodes. (auth) more
Date: January 1, 1959
Creator: Callaghan, J.B. & Williams, J.S. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

EFFECT OF TRANSFER TIME ON THE RECRYSTALLIZATION BEHAVIOR OF BETA-COOLED URANIUM

Description: A study was made of the recrystallization behavior of beta-quenched uranium by incorporating the effects of transfer time from the beta heat-treating bath to the quench media. A critical transfer lime which relates to the time required to immerse samples at a temperature above the beta-alpha transformation in a quench media directly affects the beta-cooled structure and its ease of recrystallization upon alpha phase annealing. Within the critical transfer time, the ease of recrystallization and… more
Date: January 12, 1959
Creator: Carloni, Q. C. & Lewis, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen