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Analog Stimulation of HRP In-Pile Slurry Loop Facility in the LITR

Description: An analog simulation is made of the HRP in-pile slurry loop in the LITR. The radiolytic gas pressure in the pressurizer is determined. This pressure is a result of the generation of radiolytic gas in the loop core. A graphical result is obtained showing the effect of catalyst activity and pressurizer flow rate on the pressure rise from radiolytic gas. The thermal behavior of the system is studied, and the response to various controller settings is predicted. Controller settings very near optimu… more
Date: November 28, 1960
Creator: Hinton, D. B.
Item Type: Refine your search to only Report
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Analysis of Thorex Pilot Plant Radiation Exposures During 1955

Description: The Thorex Pilot Plant at Oak Ridge National Laboratory was operated during 1955, processing reactor-irradiated thorium slugs to recover U233 and thorium and 12 MTR fuel elements to recover U235 and Np237. The radiation exposure received by operating personnel during this period averaged 60 mrcp/man-week. Most radiation exposure was received in areas that were intended to be only slightly or nonradioactive. However, because insufficient decontamination of process solutions was achieved and equi… more
Date: November 16, 1956
Creator: McCarley W. T.
Item Type: Refine your search to only Report
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Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: 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.
Item Type: Refine your search to only Report
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Compilation of Requests for Nuclear Cross Section Measurements

Description: This report is a working document of the UB AEC Nuclear Cross Sections Advisory Group and is issued about twice a year for the purpose of stimulating important cross section measurements. The requests listed in this report have originated from various Atomic Energy Commission contractors, the Advisory Committee on Reactor Physics, and the Nuclear Cross Sections Advisory Group. The distribution is limited to members of the US Nuclear Cross Sections Advisory Group (NCSAG), the US Advisory Committ… more
Date: November 4, 1960
Creator: Harvey, John A.
Item Type: Refine your search to only Report
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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

Description: 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
Item Type: Refine your search to only Report
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Design and Development of a High-Temperature High-Pressure Spectrophotometer System: Status Report

Description: On 3/14/60 the Applied Physics Corporation was awarded a subcontract for the design and development of a high-temperature high-pressure spectrophotometer system based on the Cary Model 14pm Spectrophotometer insofar as possible, and consistent with our specifications, No. CTD-2, December 16, 1959.
Date: November 12, 1960
Creator: Biggers, R. E. & Wymer, R. G.
Item Type: Refine your search to only Report
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Determination of Traces of Uranium Metal by Decomposition of the Hydride

Description: Two methods were developed for the determination of uranium metal in UF3 with other fluoride compounds. A simplified method of determination which has a relatively high degree of precision (coefficient of variation 2 per cent) is carried out by decomposing the hydride in an atmosphere of carbon dioxide and subsequently measuring the hydrogen over an aqueous solution of potassium hydroxide. The ignition of the hydride in an atmosphere of oxygen and volumetric measurement of the water at reduced … more
Date: November 9, 1955
Creator: Meyer, A. S., Jr.; McDowell, B. L. & White, J. C.
Item Type: Refine your search to only Report
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Determination of Trivalent Uranium with Methylene Blue

Description: 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… more
Date: November 22, 1955
Creator: Ross, W. J.; Meyer, A. S.; White, J. C.; Kelley, N. T. & Susano, C. D.
Item Type: Refine your search to only Report
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Electrical and Electronic Symbols & Drawing Committee

Description: This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain e… more
Date: November 1961
Creator: Bates, A.E.G
Item Type: Refine your search to only Report
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Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

Description: 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+++ pa… more
Date: November 14, 1952
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
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Electronuclear Research Division Semiannual Progress Report

Description: 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 cr… more
Date: November 18, 1954
Creator: Livingston, R. S. & Howard, F. T.
Item Type: Refine your search to only Report
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Electronuclear Research Division Semiannual Progress Report for Period Ending September 20, 1955

Description: The installations of the beam deflector in the ORL 86-inch Cyclotron is sufficiently complete to allow initial testing the system permits the optional use of high-current internal targets. A survey of [illegible] cross sections made with 14-Mev neutrons indicates qualitative agreement with statistical theory. An internal-conversion ion spectrograph and a fission-fragment spectrograph were built and put in operation. The [illegible] functions severed proton-induced reactions of possible use in i… more
Date: November 1955
Creator: Livingston, Robert S. & Howard, F. T.
Item Type: Refine your search to only Report
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Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer

Description: Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date: November 21, 1960
Creator: Fowler, T. B. & Tobias, Melvin
Item Type: Refine your search to only Report
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An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys

Description: The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed … more
Date: November 7, 1956
Creator: Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
Item Type: Refine your search to only Report
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Evaporation of Iron-, Nickel-, and Cobalt-Base Alloys at 760 to 980°C in High Vacuums

Description: 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.
Item Type: Refine your search to only Report
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Experience in the Fabrication of Uranium - 233 Bearing ThO2UO2 Rods in a Lightly Shielded Facility at ORNL

Description: The potential of the thorium fuel cycle for achieving low nuclear fuel costs is complicated by the presence of 232U associated with 233U formed in the reactor. The decay of the 232U daughters produces penetrating radiation making the consideration of shielding and fast process times mandatory. The construction and operation of a lightly shielded, semi remote factify, known as the Kilorrod Facility, in which fuel rods containing (Th-3 wt % 233U)O2 are fabricated, is the first step in determining… more
Date: November 1963
Creator: Van Cleve, J. E., Jr. & Lotts, A. L.
Item Type: Refine your search to only Report
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Experimental Determination of an Adequate Fission Chamber Location in the ORR Pool

Description: An experiment was performed at the ORR in order to find a good fission chamber location. Two locations on the pool side of the reactor tank were explored with a one inch diameter fission chamber. The thermal neutron flux attention was found to vary nearly exponentially with distance, and no shadowing effect could be seen during a reactor startup. The fission products high gamma flux could be discriminated without difficulties. Both positions seem to be adequate to locate a reactor control fissi… more
Date: November 4, 1960
Creator: Roux, D. P. & Colomb, A. L.
Item Type: Refine your search to only Report
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Homogeneous Reactor Project Quarterly Progress Report: For Period Ending October 31, 1954

Description: Part I. Experimental Reactors: The design has been completed for all the major high-pressure and low-pressure components except the reactor pressure vessel. Contained in this report are the most recent revisions of the low-pressure-system flow sheet, a description of important details of the reactor cell, and the final design of the main heat exchangers, the inner dump tanks and separator. the recombiner and recombiner-condenser, and the outer dump tank and reflux condenser. Part II. Thorium Br… more
Date: November 1954
Creator: McDuffie, H. F. & Kelly, D. C.
Item Type: Refine your search to only Report
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