Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952 (open access)

Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."
Date: November 14, 1952
Creator: Livingston, Robert S. & Howard, F. T.
System: The UNT Digital Library
Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds (open access)

Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Abstract: Technical report describing an evaluation of solvents for use in the extraction of uranium from Mallinckrodt type ore feeds.
Date: November 6, 1950
Creator: Runion, T. C.
System: The UNT Digital Library
Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds (open access)

Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Technical report evaluating solvents for use in the extraction of uranium from Mallinckrodt type ore feeds. Re-evaluates the Mallinckrodt process in the light of the more recent solvent extraction development that has been carried out at various AEC sites.
Date: November 6, 1950
Creator: Runion, T. C.
System: The UNT Digital Library
Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data (open access)

Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
System: The UNT Digital Library
A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator (open access)

A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator

Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical and experimental studies have shown that the Mc2 Cyclotron is a practical concept; high extraction efficiencies can be obtained, and the residual radiation problems are manageable. The project would require less than seven years to complete, and would cost about $43,000,000."
Date: November 1, 1963
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Solid State Division Semiannual Progress Report for Period Ending August 31, 1955 (open access)

Solid State Division Semiannual Progress Report for Period Ending August 31, 1955

LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses for fission products in the fuel, by measuring the activation of cobalt foils attached to the loop, and by activation of the loop tubing itself. The determination of the power by these various methods gave 2.5 to 2.8 kw during operation of the loop, and the maximum power density was 0.4 kw/cc. Chemical analyses of the fuel were carried out to determine U, Zr, and the major constituents of inconel: Ni, Cr, and Fe.
Date: November 16, 1955
Creator: Billington, D. S. & Crawford, J. H., Jr.
System: The UNT Digital Library
Determination of Trivalent Uranium with Methylene Blue (open access)

Determination of Trivalent Uranium with Methylene Blue

A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is 1.5 per cent for 5 mg quantities of trivalent uranium. The method was applied to various mixtures of fluoride salts containing both trivalent and tetravalent uranium.
Date: November 22, 1955
Creator: Ross, W. J.; Meyer, A. S.; White, J. C.; Kelley, N. T. & Susano, C. D.
System: The UNT Digital Library
ORNL Mortal Recovery Plant: Processing of ORNL Graphite Reactor Fuel Elements During the Period July and August, 1955 (open access)

ORNL Mortal Recovery Plant: Processing of ORNL Graphite Reactor Fuel Elements During the Period July and August, 1955

From July 7 to August 31, 1955, 20 tons of uranium and 1,200 g of plutonium were recovered in 47 days of plant operation at an average rate of 833 lb/day of uranium and at a cost of $2.60/lb of uranium. Uranium and plutonium recoveries were, respectively, 99.9 and 95.5 per cent.
Date: November 11, 1955
Creator: Brooksbank, R. E.; Chandler, J. M. & Hylton, C. D.
System: The UNT Digital Library
Preliminary Results of APPR Critical Experiments, Part I. (open access)

Preliminary Results of APPR Critical Experiments, Part I.

This memorandum is the first in a series reporting progress in the program of critical experiments in the ORNLArmy Package Power Reactor Project. The critical assembly, designated as CA-25, is analogous to the APPR design core and consists of 45 fuel boxes, in a 7 x 7 array with the corners removed, contaIned in a large water tank. Two sides of each box are slotted for the insertion and positioning of any desired loading of eighteen plates of fuel, structural material, and poison. The array is submerged in water to provide a moderated and reflector. Enriched uranium metal, in two-mil-thick foils 2.5 x 22 in, is encased in type 304 stainless steel sheets, 2.7 x 23 x 0.0105 in., to form fuel plates. Stainless steel plates, 2.7 x 23 x 0.025 in. are used to simulate additional steel in the APPR core. It is, therefore, possible to maintain an essentially constant metal to water ration in the assembly when the fuel content is varied. The fuel is distributed as uniformly as possible in all boxes and a symmetrical distribution of materials is maintained in the core at all times. Fuel plates containing half-width (1.25 in) uranium foils are provided for …
Date: November 25, 1955
Creator: Williams, D. V. P.
System: The UNT Digital Library
Electronuclear Research Division Semiannual Progress Report (open access)

Electronuclear Research Division Semiannual Progress Report

Nuclear physics research with 22-Mev protons in the 86-in. cyclotron included angular-distribution measurements of neutrons from (p,n) reactions in nine target elements; measurement of the angular distribution of fission fragments from proton-induced fission of U233, U225, U228, Th230, and Th232; measurement of alpha-particle angular distributions from (p,α) reactions a study of the neutron-deficient isotopes of terbium and completion of an extensive program of the measurement of activation cross sections. Two more targets for cyclotron production of isotopes were developed, and the production yields for 14 radioisotopes are summarized. A new record for continuous beam power on a production target, 36 kw for 5 hr, was achieved. The design of a beam-deflector system for the 86-in. cyclotron has been completed, and several of the components have been fabricated ; a shutdown for installation is scheduled for October 8. The deflected N+++ beam of the 63-in. cyclotron was used in a study of the gain and loss of electrons by nitrogen lens passing through thin foils, and the equilibrium charge distribution of lens as a function of energy was thus obtained. The excitation functions were measured for nitrogen-induced reactions on both nitrogen and oxygen. Assembly restrictions of the prepared 114-in. heavy-particle cyclotron …
Date: November 18, 1954
Creator: Livingston, R. S. & Howard, F. T.
System: The UNT Digital Library
General Reactor-Engineering Research Quarterly Progress Report [for] Period Ending August 31, 1950 (open access)

General Reactor-Engineering Research Quarterly Progress Report [for] Period Ending August 31, 1950

Technical report describing results on work which cannot be ascribed to one reactor program. Outlines the results of miscellaneous corrosion testing, the development of new shielding materials, the testing of irradiated plastics, and general heat transfer investigation. [From Preface]
Date: November 13, 1950
Creator: Lyon, R. N.
System: The UNT Digital Library
Mathematics Panel Quarterly Progress Report [for] the Period Ending July 31, 1951 (open access)

Mathematics Panel Quarterly Progress Report [for] the Period Ending July 31, 1951

Technical report describing work on two special projects: (1) the Oak Ridge Computer; and (2) numerical integration of differential equations; multipoint boundary problems. The reports also describes work on thirty special problems.
Date: November 26, 1951
Creator: Householder, A. S.
System: The UNT Digital Library
Physics of Solids Institute Quarterly Progress Report [for] Period Ending April 30, 1951 (open access)

Physics of Solids Institute Quarterly Progress Report [for] Period Ending April 30, 1951

Technical report outlining the building status, crystal physics, solid state reactions, radiation metallurgy, engineering properties, and liquid fuels activities of the Physics of Solids Institute in period ending April 30, 1951. [From Introduction and Summary]
Date: November 26, 1951
Creator: Billington, D. S. & Howe, J. T.
System: The UNT Digital Library
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956 (open access)

Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: September 1960 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: September 1960

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: November 11, 1960
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964 (open access)

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress is presented. This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Briggs, R. B.
System: The UNT Digital Library
Solid State Division Annual Progress Report for Period Ending August 31, 1957 (open access)

Solid State Division Annual Progress Report for Period Ending August 31, 1957

Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Solid State Division. Work and research progress made during 1957 is presented. This report includes tables, illustrations, and photographs.
Date: November 26, 1957
Creator: Billington, D. S. & Crawford, J. H., Jr.
System: The UNT Digital Library
Fall-Out in Southeastern United States During January and February 1951 from the Nevada Atomic Tests (open access)

Fall-Out in Southeastern United States During January and February 1951 from the Nevada Atomic Tests

Air filter and rainwater collections of atmospheric fall-out were made at Atlanta, Georgia; Urbana, Illinois; Topeka, Kansas; Fort Worth, Texas; and Nashville, Tennessee. Collections reflect the effects of the radioactive cloud from the Nevada tests.
Date: November 27, 1951
Creator: Davis, F. J.
System: The UNT Digital Library
Nuclear Energy Centers : Industrial and Agro-Industrial Complexes (open access)

Nuclear Energy Centers : Industrial and Agro-Industrial Complexes

Report regarding the use of low cost nuclear power to increase both industrial and agricultural production, especially in developing nations.
Date: November 1968
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960 (open access)

Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960

From introduction: "This is the sixth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: November 1961
Creator: Pennington, R. T.
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1958 (open access)

Health Physics Division Annual Progress Report, July 31, 1958

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: November 10, 1958
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report, July 1, 1959 (open access)

Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date: November 2, 1959
Creator: Oak Ridge National Laboratory. Instrumentation and Controls Division.
System: The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961 (open access)

Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961

Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date: November 1968
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums (open access)

Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Report issued by the Oak Ridge National Laboratory discussing the evaporation of alloys in high vacuums. As stated in the introduction, "the investigation encompasses measurements of the evaporation rates, identification of the evaporating elements, and correlation of these measurements to the alloy composition for specimens in both the polished and oxidized conditions" (p. 2). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Bourgette, D. T.
System: The UNT Digital Library