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TEST OF GERMAN UNDERGROUND PERSONNEL SHELTERS

Description: The predicted behavior of German underground personnel shelters, equipment, and certain instrumentation was investigated. Data obtained will be used for evaluation and improvement of present design criteria. Nine reinforcedconcrete underground shelters, designed by German engineers, were tested at the 170-, 155-, 110-, 78-, 26-, 11.5-, and 7.2-psi overpressure ranges as determined from average blast-line instrumentation measurements. Reinforcing steel, doors, and ventilation equipment were rece… more
Date: July 1, 1960
Creator: Cohen, E. & Bottenhofer, A.
Partner: UNT Libraries Government Documents Department
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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Partner: UNT Libraries Government Documents Department
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The Path of Carbon in Photosynthesis

Description: Biosynthesis begins with photosynthesis. Green plants and other photosynthetic organisms use the energy of absorbed visible light to make organic compounds from inorganic compounds. These organic compounds are the starting point for all other biosynthetic pathways. The products of photosynthesis provide not only the substrate material but also chemical energy for all subsequent biosynthesis. For example, nonphotosynthetic organisms making fats from sugars would first break down the sugars to sm… more
Date: October 1, 1960
Creator: Bassham, J. A. & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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FURTHERSTUDIES ON STERILITY PRODUCED IN MALE MICE BY DEUTERIUMOXIDE

Description: The authors have previously reported that deuterium oxide in the drinking water of either male or female mice produces sterility. An investigation of some of the conditions--with particular reference to time--of deuterium oxide treatment to produce sterile C{sub 57} male mice indicated that the sensitive phase of sperm production centered around the late prophase of meiosis. In some experiments, although D{sub 2}O was almost completely absent during maturation of the sperm, and when the mice ma… more
Date: June 1, 1960
Creator: Hughes, Ann M.; Bennett, Edward L. & Calvin, Melvin.
Partner: UNT Libraries Government Documents Department
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COHERENT ELECTROMAGNETIC EFFECTS IN HIGH-CURRENT PARTICLE ACCELERATORS: I. INTERACTION OF A PARTICLE BEAM WITH AN EXTERNALLY DRIVEN RADIO-FREQUENCY CAVITY

Description: A calculation is made of the interaction of a beam of particles in an accelerator with the radio-frequency cavity that provides the accelerating mechanism of the machine. A Hamiltonian for synchrotron motion is employed that makes possible the simultaneous solution of Maxwell's equations and the Vlasov equation, so that a self-consistent distribution of particles in synchrotron phase space is determined. The effective voltage on the cavity due to the beam of charged particles is of the order of… more
Date: July 1, 1960
Creator: Neil, V. Kelvin & Sessler, Andrew M.
Partner: UNT Libraries Government Documents Department
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Manual of Radiation Protection Standards

Description: "The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."
Date: March 1, 1960
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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Fuel element handling before irradiation

Description: This report on fuel element handling presents in some detail the current status of an engineering study which has been underway for some time, and which is continuing. The study was undertaken to determine if it is feasible, and if it is practicable, to revise the method and equipment used for fuel element handling with existing charging machines.
Date: February 1, 1960
Creator: Gilbert, R. D.
Partner: UNT Libraries Government Documents Department
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The High Intensity Food Irradiator: Report 17

Description: From introduction: A thorough investigation, both experimental and theoretical was carried out on plaque type radiators. Five phases of the work are reported: preliminary design analysis, experimental measurements, computational program and analytical studies, followed by a general discussion of source design principles. The results are summarized in graphs and formulae which may be applied to other design requirements.
Date: May 1, 1960
Creator: Curtiss-Wright Corporation
Partner: UNT Libraries Government Documents Department
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Design study interim report, RMA button line radiation reduction

Description: The design approach followed in this study is that of handling and processing plutonium solution and powders within tightly sealed but readily replaceable units of processing equipment, each one of which will do one step in the overall process. The presently used method is to use open equipment enclosed in glove boxes attached to a transporting device. Elimination of the glove box enclose and its replacement by tightly sealed and detachable equipment provides the accessability necessary for equ… more
Date: April 1, 1960
Creator: Kolb, J. W. & Bellarts, H. J.
Partner: UNT Libraries Government Documents Department
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Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
Partner: UNT Libraries Government Documents Department
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OMR Degasifier Loop Experiment

Description: Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
Partner: UNT Libraries Government Documents Department
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OMRE Fuel Plate Surface Temperature Measurement

Description: Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Partner: UNT Libraries Government Documents Department
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Plutonium: Enriched OMR Cores

Description: Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date: May 1, 1960
Creator: Connolly, T. J.
Partner: UNT Libraries Government Documents Department
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OMRE Fuel Removal and Shipping Equipment

Description: Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.
Date: April 1, 1960
Creator: Mallon, P. J.; Duncan, D. S. & Noyes, R. C.
Partner: UNT Libraries Government Documents Department
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Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service

Description: Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date: May 1, 1960
Creator: Baroczy, C. J.
Partner: UNT Libraries Government Documents Department
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300,000-KWE SGR Nuclear Power Plant of Current Technology

Description: Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date: August 1, 1960
Creator: Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
Partner: UNT Libraries Government Documents Department
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