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75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY
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.
Object Type:
Report
System:
The UNT Digital Library
The Abilene Reporter-News (Abilene, Tex.), Vol. 79, No. 199, Ed. 1 Friday, January 1, 1960
Daily newspaper from Abilene, Texas that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
unknown
Object Type:
Newspaper
System:
The Portal to Texas History
The Ada Evening News (Ada, Okla.), Vol. 56, No. 250, Ed. 1 Friday, January 1, 1960
Daily newspaper from Ada, Oklahoma that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
Little, W. D.
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
ADVANCED CRITICAL EXPERIMENT SAFEGUARDS REPORT. SUPPLEMENT NO. 2. NUSU PHASE B AND C.
None
Date:
January 1, 1960
Creator:
Harding, R S & Slater, M
Object Type:
Report
System:
The UNT Digital Library
Advanced Thermoelectric Power System. Final Report
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 pound (exclusive of the weight of the heat source). (auth)
Date:
January 1, 1960
Creator:
Harvey, R. J.
Object Type:
Report
System:
The UNT Digital Library
Apparatus for Determining Linear Thermal Expansions of Materials in Vacuum or Controlled Atmosphere
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 controlled-atmosphere apparatus. Recording of data is either fully automatic or manual. The percentage error is believed to be no greater than plus or minus 0.1 to 0.2%. Original data for linear thermal expansion of materials such as hot-pressed BeO, hafnium-free ZrC/sub 2/, zirconium-free HfO/sub 2/, INOR-8 alloy, siliconized silicon carbide, uranium dioxide, compositions of Be + BeO, and samples of CS 312 graphite, boron nitride, and tungsten metal. (auth)
Date:
January 1, 1960
Creator:
Fulkerson, S. D.
Object Type:
Report
System:
The UNT Digital Library
Argonaut Automatic Flux Controller Design Report
None
Date:
January 1, 1960
Creator:
Gerba, A., Jr.
Object Type:
Report
System:
The UNT Digital Library
The Baytown Sun (Baytown, Tex.), Vol. 40, No. 134, Ed. 1 Friday, January 1, 1960
Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
Hartman, Fred
Object Type:
Newspaper
System:
The Portal to Texas History
BEHAVIOR OF RUBBING MOLYBDENUM SURFACE IN SODIUM ENVIRONMENTS
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 also found to be temperature dependent. Addition of clean sodium between dry rubbing molybdenum surfaces in an argon atmosphere of high purity produced a marked drop in friction coefficient, and the character of the wear scar changed from galling to superficial scratching. Furthermore, these effects persisted after removal of sodium by evaperation. Studies of the films formed on molybdenum surfaces during sliding in liquid sodium and under controlled atmospheres were carried out using electron and x-ray diffraction, electron microscope, and differential thermal-analysis techniques. It was established that a sodium molybdate film on the molybdenum surfaces can be associated with low friction and diminished surface damage. Studies in vacuums up to 10/sup -6/ mm of mercury showed that native oxides on molybdenum also …
Date:
January 1, 1960
Creator:
Kissel, J.W.; Melton, C.W. & Glaeser, W.A.
Object Type:
Report
System:
The UNT Digital Library
Blackwell Journal-Tribune (Blackwell, Okla.), Vol. 66, No. 10, Ed. 1 Friday, January 1, 1960
Daily newspaper from Blackwell, Oklahoma that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
unknown
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
The Boswell News (Boswell, Okla.), Vol. 58, No. 8, Ed. 1 Friday, January 1, 1960
Weekly newspaper from Boswell, Oklahoma that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
Mills, Wayne
Object Type:
Newspaper
System:
The Gateway to Oklahoma History
Brownwood Bulletin (Brownwood, Tex.), Vol. 60, No. 67, Ed. 1 Friday, January 1, 1960
Daily newspaper from Brownwood, Texas that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
Coppedge, Don L.
Object Type:
Newspaper
System:
The Portal to Texas History
A Calculational Method for the Determination of Surface Tensions From Photographed Menisci--With Application to Water and Mercury
None
Date:
January 1, 1960
Creator:
Biery, J. C. & Oblak, J. M.
Object Type:
Report
System:
The UNT Digital Library
The Carrollton Chronicle (Carrollton, Tex.), Vol. 56, No. 6, Ed. 1 Friday, January 1, 1960
Weekly newspaper from Carrollton, Texas that includes local, state, and national news along with advertising.
Date:
January 1, 1960
Creator:
Sindik, Nicholas J.
Object Type:
Newspaper
System:
The Portal to Texas History
CEND CRITICAL FACILITIES OPERATIONS MANUAL. BONUS CRITICAL EXPERIMENT.
None
Date:
January 1, 1960
Creator:
Knapp, R W
Object Type:
Report
System:
The UNT Digital Library
CEND CRITICAL FACILITIES SAFEGUARDS REPORT: BONUS CRITICAL EXPERIMENT.
None
Date:
January 1, 1960
Creator:
Knapp, R W
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program.
This report presents a brief survey of the current status of technology on organic-cooled reactors.
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 1. Summary of Technical and Economic Status as of 1959
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 2. Economic Potential and Development Program as of 1959
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 3. Book 2. Status Report on Pressurized Water Reactors as of 1959
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
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 3. Book 3. Status Report on Aqueous Homogeneous Reactors as of 1959
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 fuel and blanket materials for removal of fission and corrosion products and recovery of fissionable material is discussed. A flowsheet for the preparation of ThO/sub 2/ slurries is contained. Development studies on reactor components, systems, instrumentation, and control are reviewed. Reactor-control, safety, and criticality studies are discusspd. (C.J.G.)
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 3. Book 4. Status Report on Heavy Water Moderated Reactors as of 1959
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 developed. Other areas in which additional work must be done are the reactivities of various fuel lattices. fuel element burnout (especially for the boiling regime), zirconium pressure tubes and their connections to steel, and methods of reducing and detecting D/sub 2/O leakage. (auth)
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 3. Book 5. Status Report on Boiling Water Reactors Technology as of 1959
This report addresses the status report on boiling water reactor technology as of 1959.
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Civilian Power Reactor Program. Part 3. Book 6. Status Report on Sodium Graphite Reactors as of 1959
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 constnuction phase. (W.D.M.)
Date:
January 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library