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An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders

Description: From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
Date: August 15, 1952
Creator: Harman, Cameron G.; Shinn, J., Jr. & Wagner, H. E.
Partner: UNT Libraries Government Documents Department
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Hydrogen Embrittlement of Zirconium

Description: Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure,… more
Date: August 22, 1952
Creator: Dayton, Russell Wendt; Schwope, A. D.; Muehlenkamp, G. T.; Saller, Henry A.; Dickerson, R. F.; Schwartz, C. M. et al.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Partner: UNT Libraries Government Documents Department
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Mammalian Radiation Genetics

Description: "This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in … more
Date: August 11, 1952
Creator: Russell, W. L.
Partner: UNT Libraries Government Documents Department
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Organo-Phosphorous Compounds for Solvent Extraction

Description: From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher … more
Date: August 14, 1952
Creator: Higgins, C. E.; Baldwin, W. H. & Ruth, J. M.
Partner: UNT Libraries Government Documents Department
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Protective Equipment Evaluation Program Quarterly Progress Report: July-September 1951

Description: This quarterly progress details the ongoing work of the Protective Equipment Evaluation Program at the Oak Ridge National Laboratory. Topics discussed include aerosol generation, penetration studies, particle size measurement, and an appendix with analytical methods.
Date: August 6, 1952
Creator: Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Heat Transfer and Pressure Loss in Tube Bundles for High Performance Heat Exchangers and Fuel Elements

Description: From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this… more
Date: August 12, 1952
Creator: Cohen, G. H.; Fraas, A. P. & LaVerne, M. E.
Partner: UNT Libraries Government Documents Department
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Laboratory Development of the MTR-RaLa Process for the Production of Barium140

Description: From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).
Date: August 19, 1952
Creator: Blanco, R. E., (Raymond Eugene), 1918-1987; Kibbey, A. H.; Pannell, J. H.; Shank, E. M.; Farmer, J. E.; Helton, D. M. et al.
Partner: UNT Libraries Government Documents Department
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Recycle of 231 Building supernates to 224 T Building: Relationship to ``T`` and ``S`` Plant

Description: An examination of the process scheme for handling present and future 231 Building supernatant solutions is necessary to forecast the effects of placing one of the processing facilities (224B) in a standby status and to ascertain if rescheduling of any of the supernatant solutions to 202S will be necessary. The examination indicates the 231 Building process supernates and cell cleanouts together with the 221, 224T Buildings acid washes and the 234-5 Building returns can be processed through the … more
Date: August 20, 1952
Creator: Packer, G. V. & Schmidt, W. C.
Partner: UNT Libraries Government Documents Department
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The Determination of Americium in Plutonium Product Solutions

Description: The following report describes the process to determine the method for determination of americium in the presence of plutonium and uranium.
Date: August 15, 1952
Creator: Chetham-Strode, A., Jr.
Partner: UNT Libraries Government Documents Department
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Diffusion Length Measures in the DR and H Piles

Description: The following report investigates tests on diffusion length and contamination performed on graphite laid up in 105-DR and 105-H piles.
Date: August 1952
Creator: Montgomery, E. B.
Partner: UNT Libraries Government Documents Department
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Behavior of S.I.R. Fuels Irradiated in Sodium: Final Report, Production Test 105-180-P (Special Request KAPL-79: The "Beta Experiment")

Description: Report describing the effects of pile irradiation on fuel materials and coil springs for the Submarine Intermediate Reactor. The investigation was called for by Hanford Irradiation Request No. 79. Results of investigation are detailed in the report.
Date: August 12, 1952
Creator: Lambert, J. B., 1929-
Partner: UNT Libraries Government Documents Department
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Corrosion Test of Type 502 Stainless Steel

Description: The following report provides complete data and test procedure from hot water corrosion tests of type 502 stainless steel.
Date: August 13, 1952
Creator: Zimmerman, D. L.
Partner: UNT Libraries Government Documents Department
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High Amperage Slug Welding : Final Report [on] 313-120-M

Description: This report presents data recorded during a program made to improve uranium slug quality in January, 1952, to determine what improvements could be made in the welding process.
Date: August 15, 1952
Creator: Lingafelter, J. W.
Partner: UNT Libraries Government Documents Department
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Hanford Works Monthly Report: July 1952

Description: This is a progress report of the production reactors on the Hanford Reservation for the month of July 1952. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.
Date: August 15, 1952
Creator: Prout, G. R.
Partner: UNT Libraries Government Documents Department
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Storage of radioactive aqueous wastes from Purex processes

Description: The radioactive liquid wastes from a separations facility are customarily stored in underground waste storage tanks. The wastes from the proposed Purex Separations Plant will have a high concentration of the fission products and will result in a large evolution of heat. The possibility of these wastes boiling due to radio-disintegration of fission products has made a survey of the problem desirable. This report lists the results of this investigation.
Date: August 1, 1952
Creator: Platt, A. M. & Krieg, J. T.
Partner: UNT Libraries Government Documents Department
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Mechanical development studies technical activities report, July 1952

Description: Described herein are studies on pile control, shielding, process tube assembly, pile operating equipment, pile renovation, power recovery, pile piping and the 189-D test laboratory at Hanford.
Date: August 12, 1952
Creator: Alexander, W. K.
Partner: UNT Libraries Government Documents Department
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Activation Energy for Fission

Description: The experimentally determined exponential dependence of spontaneous fission rate on Z{sup 2}/A has been used to derive an expression for the dependence of the fission activation energy on Z{sup 2}/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.
Date: August 29, 1952
Creator: Seaborg, Glenn T.
Partner: UNT Libraries Government Documents Department
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