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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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Advanced Thermoelectric Power System. Final Report

Description: Development of a radioisotope-fueled thermoelectric power-conversion system for the SNAP program is discussed. The generator operates at somewhat less than 1% over-all efficiency, has a power output of approximately 1.45 watts, and has a specific power of 0.l42 watts per pound. The power-flattening device did not perform as expected. A second generator is also described which produces a maximum power of 1.6 watts, has a maximum efficiency of 1.20%, and has a specific power of 0.32 watts per pou… more
Date: January 1, 1960
Creator: Harvey, R. J.
Partner: UNT Libraries Government Documents Department
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Apparatus for Determining Linear Thermal Expansions of Materials in Vacuum or Controlled Atmosphere

Description: An apparatus for determining linear thermal expansion data up to 1350 deg C for materials that cannot be heated in air is described. Expansion is not measured directly, but is derived from the differential expansion between the material being tested and the materials of construction of the dilatometer. The apparatus is calibrated against published data on the linear thermal expansion of both fused silica and polycrystalline tungsten metal. It can be operated either as a high-vacuum or as a cont… more
Date: January 1, 1960
Creator: Fulkerson, S. D.
Partner: UNT Libraries Government Documents Department
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BEHAVIOR OF RUBBING MOLYBDENUM SURFACE IN SODIUM ENVIRONMENTS

Description: A study has been made of the wear and friction phenomena associated with sliding molybdenum surfaces lubricated by liquid sodium. Operating conditions included sodium temperatures from 250 to 1300 deg F, sliding speeds of from 0.22 to 2.5 nan per sec, and contact stresses of 80,000 psi. Sliding specimens consisted of a ball and a flat rectangle. Sodium was found to influence the sliding behavior of molybdenum by modifying reacted films which provided boundary lubrication. These effects were als… more
Date: January 1, 1960
Creator: Kissel, J.W.; Melton, C.W. & Glaeser, W.A.
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program.

Description: This report presents a brief survey of the current status of technology on organic-cooled reactors.
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 1. Summary of Technical and Economic Status as of 1959

Description: The current technical and economic status for each reactor concept in the Civilian Power Reactor Program is summarized. The individual techical status reports which present detailed information will be published by AEC as TID-8518. Included in this summary are: power costs for various reactor types versus coal- fired plants; construction schedule for heavy-water natural-U reactors; and annual program costs. (T.R.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 2. Economic Potential and Development Program as of 1959

Description: The status of technology of nuclear power reactors in 1959 is reviewed. General research and engineering development activities are discussed. The reactors considered include the pressurized water, boiling water, light water moderated superheat, organic cooled, sodium graphite, gas cooled enriched fuel, gas cooled natural uranium, fast breeder, aqueous homogeneous, and heavy water. Power costs are compared with the cost of power from conventional plants. (C.H.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 2. Status Report on Pressurized Water Reactors as of 1959

Description: The status of pressurized water reactors on a technical, economic, and operating experience basis is reported. Items covered include concept description, PWR objectives, general research and development prcgram, reactor data, reactor illustrations, operating experience, construction and operation schedules, and present limitations and problems. (W.D.M.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 3. Status Report on Aqueous Homogeneous Reactors as of 1959

Description: The status of a program to develop a thermal breeder power reactor which is based on the Th-U/sup 233/ cycle is discussed. The general characteristics of two-region power breeder reactors which are either solution-core slurryblanket or slurry-core slurry-blanket are described. A review of studies on corrosion, physical properties, and metallurgy of fuel materials, in particular aqueous ThO/ sub 2/ suspensions, is presented. Development studies on cladding alloys are discussed. The processing of… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 4. Status Report on Heavy Water Moderated Reactors as of 1959

Description: Estimates indicate that, within the D/sub 2/O-moderated natural-uranium- fuel reactor category, the lowest cost reactor will be cooled by boiling D/sub 2/ O. The margin over nonboiling is small, especially for reactors in the 100Mw(e) size and smaller. A major area in which research must be advanced before any of the reactor concepts can be successful is fuel-element fabrication and irradiation behavior. Both oxide and metallic elements have their own advantages, and each type should be develop… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book 6. Status Report on Sodium Graphite Reactors as of 1959

Description: The current development status of the sodium graphite reactor concept is described. The development history is summarized, and all important areas of development are discussed. The discussion of the SGR program is broken into three categories: (1) general research and development, dealing with reactor physics, fuels and materials, components, etc., (2) experimental reactors, operating or in some phase of design or constnuction, and (3) power demonstration reactors, operating or in a design or c… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Book I. Status Report on Fast Reactors as of 1959

Description: A description of fast reactor types is given and the objectives of the AEC program on fast reactors are outlined. General research and development programs completed and in process on physics, fuel and materials, heat transfer, fluid flow, coolant chemistry, reactor safety, and components and systems are discussed. Reactors completed, under design and construction, and under study are described. (W.D.M.) A general description of ship and power plant, tabulation of principle characteristics, eco… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 3. Status Report on Gas-Cooled Reactors as of 1959. Book 8

Description: The technology of natural-uranium-fueled graphitemoderated gas-cooled reactor power plants is summarized for its relevance to the technology of enriched-fuel graphite-moderated systems. The technology of D/sub 2/Omoderated gas-cooled reactors is also summarized. Estimated technical performance parameters are given for the enriched-fuel prototype and for a large natural- uraniumfueled plant. Current technical status is discussed in terms of reactor physics, heat transfer and fluid flow, core mat… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Civilian Power Reactor Program. Part 4. Plans for Development as of February 1960

Description: In developing the program plans presented, primary attention was given to the technological development required to achieve economically competitive nuclear power. The program objectives are given in brief and the specific reactor program is discussed in some detail. The nuclear technology program is summarized. (W.D.M.)
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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CONTROL AND DYNAMICS PERFORMANCE OF A SODIUM COOLED REACTOR POWER SYSTEM

Description: In an attempt to prove the feasibility of liquid sodium as a reactor coolant, a design stady of three vital system components was undertaken: the intermediate exchanger, the boiler, and the superheater. Investigation shows that, during transient changes in load, the steam and sodium systems' temperature changes will not significantly exceed the small steady-state temperature changes, provided that the control system mairtains the design steady-state ratio between the flow rates and power level … more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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The Decontamination and Recovery of Precious Meatals. Quarterly Progress Report Period from April 1, 1960 to July 1, 1960,

Description: This report is the first quarterly report under Contract AT(30-1)-2528 for the decontamination and recovery of precious metals from contaminated scrap. This program encompasses the recovery of gold, platinum, iridium, rhodium and palladium from scrap and contaminated laboratory ware, equipment, etc. which may be contaminated by alpha emitters (i.e., uranium, plutonium and possibly polonium or combinations of these), beta-gamma emitters such as fission products or all three sources of radiation.… more
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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Deflections and Load Distributions in Linear Elastic Structures--CTAC and Mode Codes

Description: Since the stress analysis of a complicated statically indeterminate structure involves the handling of many simultaneous equations, the S0207 code for the IBM-650 was developed at Bettis to solve this problem by the use of matrix transformations. The code has two parts, each with a title: (a) the CTAC code gives stresses, deflections, and reactions: and (b) the MODE code calculates natural frequencies and modes of vibration. As an aid to users of the code, a review is given of the elasticity an… more
Date: January 1960
Creator: Friedrich, C. M.
Partner: UNT Libraries Government Documents Department
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The Determination Thorium Isotopic Ratios by Radiochemical Methods

Description: >A sensitive analytical method was needed to determine the total thorium content and the Th/sup 2//sup 3//sup 0/ isotopic abundance in a number of uranium ore and mill talling samples available in the United States. A procedure was developed using absolute alpha counting to determine Th/sup 2//sup 3//sup 0/ and neutron activation analysis to determine Th/sup 2//sup 3//sup 2/. The method is highly specific with a sensitivity on the order of 10/sup -//sup 1//sup 0/ grams for either isotope and wa… more
Date: January 1, 1960
Creator: Matsumoto, W. Y.
Partner: UNT Libraries Government Documents Department
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Development Plan for Multi-Purpose Compact Nuclear Power Systems (Snap 4).

Description: This document resents the development program for the SNAP 4 Compact Power System. The development plan leads to the development of two power plant concepts that use an identical reactor but differ only in the power conversion systems.
Date: January 1, 1960
Partner: UNT Libraries Government Documents Department
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