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Capacities of Stacks in Sanitary Drainage Systems for Buildings

Description: "Some of the important results obtained in investigations of capacities of plumbing stacks in test systems at the National Bureau of Standards and elsewhere are discussed. Data are shown from experiments on the flow of water and air in such systems, and analyses of certain flow phenomena are given. Methods are shown for applying the results of research in hydraulics and pneumatics to the preparation of loading tables (for drainage and vent stacks) suitable for use in plumbing codes" (p. 1).
Date: July 3, 1961
Creator: Wyly, Robert S. & Eaton, Herbert N.
Partner: UNT Libraries Government Documents Department
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Numerical Results for EGCR Moderator-Element Stress Problems

Description: From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date: July 3, 1961
Creator: Hulbert, Lewis E. & Redmond, Robert F.
Partner: UNT Libraries Government Documents Department
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Extrusion of I&E ``O`` size tubing to finalize the process. Experiment No. U-31

Description: Work has been progressing on the development of an extrusion process for I&E tubing. The ultimate object of this development project is to compare the extrusion process from a cost standpoint with, the presently used rolling-drilling process. Various experiments have been performed to determine the optimum billet I.D., the proper follower block technique, the proper tooling parameters for the process, and the proper metallurgical structure of the material for optimum results. This extrusion com… more
Date: February 3, 1961
Creator: Frazier, D.S. & Puterbaugh, J.F.
Partner: UNT Libraries Government Documents Department
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Analysis of P&W NJ-18A Power Plant Pressure Drop Between Compressor Discharge and Turbine Inlet

Description: This study is part of an evaluation of the P&W NJ- 18A powerplant. The work presented here specifically estimates the pressure drop between the compressor discharge and the turbine inlet. Analysis was asked for two operating conditions. One was for sea level sprint at a Mach no. of 0.9, while the other was for a Mach no. of 0.9 at 35000 ft.
Date: January 3, 1961
Creator: Casagrande, R. D.
Partner: UNT Libraries Government Documents Department
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Re-evaluation of metal performance levels of C-II-N and C-II-E material

Description: This report presents an analysis of rupture experience at C Reactor over the past two years. The purpose of the study was to provide a basis for revising, if necessary, the current metal performance level multipliers for C-II-N and C-II-E material.
Date: March 3, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Measured cadmium burnup in C reactor HCR`s

Description: C Reactor horizontal control rods were originally designed to have 32 feet of poison, made of 64 six inch ``cans`` each consisting of two concentric cylinders sealed at each end and the annular space between them filled with boron carbide powder. It was discovered before startup that under irradiation the neutron, alpha reaction in the boron could cause a pressure buildup and rupture of the sealed section. As an expediency cylinders wrapped with 72 miles thick cadmium metal were substituted for… more
Date: May 3, 1961
Creator: Chitwood, R. A.
Partner: UNT Libraries Government Documents Department
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In-tank solidification of intermediate-activity wastes

Description: Solidification of intermediate-activity wastes is a major goal of the CPD Waste Management Program. Plans are to reduce the wastes, by evaporation, to salt cakes in existing tanks, thereby insuring safe, long-term storage of contained fission products regardless.of tank integrity. Initiation of these plans at an early date is necessary to offset the expected increase in tank failures and to provide space for future wastes. Major decisions of the program relate to selection of the evaporative me… more
Date: April 3, 1961
Creator: Campbell, B. F.
Partner: UNT Libraries Government Documents Department
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Post-irradiation examination of bumper elements with high in-reactor weight losses (RM-418)

Description: This report discusses three natural uranium, X-8001 aluminum clad, I&E Hanford production fuel elements, which were irradiated in 3363-D as part of PT-IP-262-A, were selected for detailed examination in the Radiometallurgy Laboratory. The three pieces were from the same tube and each had lost about 15 grams of cladding during irradiation. Examination was requested to determine the extent of the corrosion and whether the attack was uniform or localized. Also, measurement of the uranium fuel was … more
Date: April 3, 1961
Creator: Gruber, W. J.
Partner: UNT Libraries Government Documents Department
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Project CGC-897--Title I design, fission product storage in B-Plant

Description: A previous study described proposed facilities at B-Plant which integrate future fission product and waste calcination activities. However, in the reactivation of B-Plant in accordance with this study, heavy expenditures, above budgeted funds, would be required at an early date for Phase 1 process changes coupled with general rehabilitation work and facilities for updating of radiological control. Since waste calcination activities in B-Plant are not scheduled until Fiscal Year 1966, the expens… more
Date: April 3, 1961
Creator: Caudill, H. L. & Zahn, L. L. Jr.
Partner: UNT Libraries Government Documents Department
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The Sparker, a Divice to Overcome the Multipactor Difficulty in Starting the Oscillator of a Cycloton

Description: "Evacuated electrical oscillating cavities frequently are found to exhibit a strong loading due to electron (or iron) multiplications, the so-called multipactor effect. This effect tends to prevent the buildup of dee voltage in cyclotrons. In conventional cyclotrons driven from external oscillators having their own resonant tank circuits the difficulties are usually slight, but in cyclotrons using a simple dee system as the tank circuit difficulties are encountered in getting the oscillator t… more
Date: January 3, 1961
Creator: Fulbright, H.W.
Partner: UNT Libraries Government Documents Department
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The Nuclear Spin Of Neodymium-141

Description: The spin of neodymium-141 was measured by the method of atomic beams and found to be 3/2. A lower limit placed on the hyperfine separation of the states with total angular momentum [formula] by second-order perturbation theory shows [formula]. A prerequisite for the determination of the nuclear spin from hyperfine-structure measurements is the knowledge of the electronic structure. The ground-state configuration of neodymium is known and the value is used throughout this work.
Date: July 3, 1961
Creator: Alpert, Seymour S.; Budick, Burton; Lipworth, Edgar & Marrus, Richard
Partner: UNT Libraries Government Documents Department
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Large High Power Density Core - Interim Report I: Physics Description of Reference Design

Description: A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.
Date: February 3, 1961
Creator: Miller, C. L.
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Progress Report for October-November 1960

Description: Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain r… more
Date: March 3, 1961
Creator: Brown, K. B.
Partner: UNT Libraries Government Documents Department
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Progress Report - Pneumatic Temperature Measuring System

Description: This research report details developments in the effort to predict the speed of response of the basic pneumatic probe at the Oak Ridge National Laboratory.
Date: March 3, 1961
Creator: Hochreiter, H.M.
Partner: UNT Libraries Government Documents Department
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Operation of the EGCR Purification System Prototype

Description: Tests were conducted on a small-scale model of the experimental gas-cooled reactor (EGCR) at the Oak Ridge National Laboratory to determine the effectiveness of the system in removing gaseous impurities from circulating helium. Results indicated that hydrogen, carbon monoxide, and methane could be satisfactorily removed by oxidation in a catalytic converter.
Date: April 3, 1961
Creator: MacPherson, R.E.
Partner: UNT Libraries Government Documents Department
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