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Results:
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T = 0 and T = 1 Pairing in Light Nuclei.
None
Date:
January 1, 1969
Creator:
Goodman, A. L.
Object Type:
Thesis or Dissertation
System:
The UNT Digital Library
E-1 Common Analog Model (U)
This report is the descriptive description of the E-1 common analog model
Date:
July 1, 1969
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
[3 men pictured at WBAP's new tower site]
Photograph of three men holding a golden shovel in front of a distant radio tower.
Date:
June 1, 1964
Creator:
WBAP-TV (Television station : Fort Worth, Tex.)
Object Type:
Photograph
System:
The UNT Digital Library
13-Watt Curium Fueled Thermoelectric Generator for a Six-Month Space Mission. Final Report
None
Date:
July 1, 1960
Creator:
Bloom, J. L.
Object Type:
Report
System:
The UNT Digital Library
13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8
Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date:
August 1, 1960
Creator:
Bloom, J. L.
Object Type:
Report
System:
The UNT Digital Library
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959
The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results …
Date:
September 1, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
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
A 90$sup 0$ $sup 3$He NEUTRON SPECTROMETER.
None
Date:
January 1, 1967
Creator:
Brown, W.K.; Ellis, A.N. & Peterson, D.D.
Object Type:
Report
System:
The UNT Digital Library
100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report
A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)
Date:
May 1, 1960
Creator:
Weddell, J. B. & Bloom, J.
Object Type:
Report
System:
The UNT Digital Library
A 200 Bev ACCELERATOR EMPLOYING A SEPARATED FUNCTION MAGNET LATTICE
None
Date:
August 1, 1966
Creator:
Danby, G. T.; Allinger, J. E. & Jackson, J. W.
Object Type:
Report
System:
The UNT Digital Library
A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application
The limited supply of relatively long-half-life isotopes having a reasonably high power density and the low conversion efficiencies obtainable with thermoelectric devices have so far limited the power output of isotope-fueled sources of electric power to several tens of watts. In addition, the high cost of the available isotopes results in a very large expense for isotope-fueled generators producing several hundred watts. It appears that a small, minimumweight, conduction-cooled reactor is an attractive alternate to the isotope-fueled power supplies in the 200-w size range. The proposed reactor is a small, high-density fast core of U/sup 233/ surrounded by a beryllium reflector. This approach, generally speaking, gives a reactor that is more compact and of lighter weight than can be obtained with a moderated system having a softer neutron spectrum. In the reactor design, the path of heat flow is from the core to the inner reflector and then to the thermoelements in close contact with the inner reflector. The reject heat flowing from the thermoelement cold junctions enters the outer pontion of the reflector, which acts as the heat sink and conducts the reject heat to the large, circular, tapered-fin radiator which is attached to the reflector. Survey physics calculations …
Date:
March 1, 1963
Creator:
MacFarlane, D. R.
Object Type:
Report
System:
The UNT Digital Library
244-AR Vault Information Manual.
None
Date:
January 1, 1968
Creator:
Francis, C. J.
Object Type:
Report
System:
The UNT Digital Library
250-Watt(e) Isotope-Fueled Thermionic Generator Study. Final Report.
None
Date:
January 1, 1963
Creator:
Kortier, W. E. & Lyon, W. C.
Object Type:
Report
System:
The UNT Digital Library
250-Watt Radioisotope Thermoelectric Generator Feasibility Study. Volume 3. RTG Handling System Analysis and Design. Final Report.
None
Date:
January 1, 1966
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology
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.
Object Type:
Report
System:
The UNT Digital Library
EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies
ESE-171: This EN run was made to determine if there is any relationship between the H-5 transistor electrical characteristics, the assembly processes, and slow warm-up of the MC-890 Power Supply. Included is the test data on the H-5 transistors and the results of the High Temperature Life Test (185 {degrees}F) of 380 MC-890 Power Supplies.
Date:
September 1, 1960
Creator:
Ling, R.F.
Object Type:
Report
System:
The UNT Digital Library
The 550$sup 0$F Notched High-Strain Behavior of Three Low-Strength Structural Steels.
None
Date:
January 1, 1969
Creator:
Krempl, E.E.
Object Type:
Report
System:
The UNT Digital Library
710 high-temperature gas reactor program summary report. Volume I. Summary
Declassified 6 Sep 1973. A description of the 710 Reactor concept and its significant design features is presented. A summary of the history of the 710 Program and a summary of the major technical achievements of the program are included. (13 references) (auth)
Date:
January 1, 1967
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
710 high-temperature gas reactor program summary report. Volume IV. Critical experiment and reactor physics development
Reactor physical technology development was performed and its design was explained.
Date:
January 1, 1968
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
710 reactor program. Progress report No. 17
This report is the seventeenth in a series of progress reports of the advanced high-temperature gas reactor - 710 program. This report describes the work performed and progress made from September 1 to October 31, 1965 on the following current tasks in the 710 program: Development of Refractory-Metal Fuel Elements; Critical Experiments of Fast-Spectrum, Refractory-Metal Reactors; Experimental Reactor Preliminary Design and Development; Test Facilities Design and Evaluation; and Investigations of the Application of the 710 Reactor Concept to Space Power Systems.
Date:
December 1, 1965
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
710 reactor-shield study support for manned spacecraft applications
None
Date:
April 1, 1967
Creator:
Simpson, J.D.
Object Type:
Report
System:
The UNT Digital Library
710 Reactor thermoelectric space power system concepts
Declassified 21 Sep 1973. A preliminary evaluation of the use of the 710 Reactor in an auxiliary space power system utilizing thermoelectric converters has been performed in order to determine feasibility of the concept and to define the required 710 fuel system operating conditions. Included are results of thermodynamic cycle studies and characteristics of the major components for a range of power levels. Configuration arrangements for man rated and instrument rated 50 kw(e) systems are shown. (auth)
Date:
September 1, 1967
Creator:
Flitner, D.P.
Object Type:
Report
System:
The UNT Digital Library
A 1000 HOUR TEST OF A CORROSION PRODUCT SEPARATOR UNIT IN A HAYNES ALLOY NO. 25 LOOP CONTAINING MERCURY--TEST G-16
One of the major unsolved problems affecting the life of the SNAP II Power Conversion System is the mass transfer of corrosion products by mercury and subsequent deposition. It is feared that the corrosion products might tend to accumulate in critical areas such as orifices, bearings and so forth. Therefore, this test was conducted to evaluate a corrosion product separator and to determine the influence of corrosion product removal on corrosion rate. The corrosion product separator was successful in removing 85 percent of the elements corroded from the container walls. The loop and separator, both fabricated from Haynes alloy No. 25, operated for 1000 hours. The mercury was boiled and condensed at 1100 deg F, superheated to 1190 deg F and subcooled to 325 deg F. The flow rate in this loop was much higher than in previous loops, being approximately 37 pounds of mercury per hour as contrasted with approximately l2 pounds of raercury per hour. No increase in corrosion rate was noticed as a result of the higher flow rates and velocity or by the removal of corrosion products. If this type of separator or an improved type works equally as well in the final application, the danger …
Date:
March 1, 1962
Creator:
Nejedlik, James F.
Object Type:
Report
System:
The UNT Digital Library
1000-Mw(e) METAL-FUELED FAST BREEDER REACTOR.
None
Date:
January 1, 1966
Creator:
Link, L. E.; Ayer, J. E.; Butler, D. K.; Hub, K. A.; Loewenstein, W. B.; Mecham, W. J. et al.
Object Type:
Report
System:
The UNT Digital Library