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E-1 Common Analog Model (U)
Description:
This report is the descriptive description of the E-1 common analog model
Date:
July 1, 1969
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Report
13-Watt Curium Fueled Thermoelectric Generator for a Six-Month Space Mission. Final Report
Description:
No Description Available.
Date:
July 1, 1960
Creator:
Bloom, J. L.
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Report
13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8
Description:
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.
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Report
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
Description:
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…
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Date:
September 1, 1960
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Report
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.
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Report
A 90$sup 0$ $sup 3$He NEUTRON SPECTROMETER.
Description:
No Description Available.
Date:
January 1, 1967
Creator:
Brown, W.K.; Ellis, A.N. & Peterson, D.D.
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Report
100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report
Description:
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 rad…
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Date:
May 1, 1960
Creator:
Weddell, J. B. & Bloom, J.
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Report
A 200 Bev ACCELERATOR EMPLOYING A SEPARATED FUNCTION MAGNET LATTICE
Description:
No Description Available.
Date:
August 1, 1966
Creator:
Danby, G. T.; Allinger, J. E. & Jackson, J. W.
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Report
A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application
Description:
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 a…
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Date:
March 1, 1963
Creator:
MacFarlane, D. R.
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Report
244-AR Vault Information Manual.
Description:
No Description Available.
Date:
January 1, 1968
Creator:
Francis, C. J.
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Report
250-Watt(e) Isotope-Fueled Thermionic Generator Study. Final Report.
Description:
No Description Available.
Date:
January 1, 1963
Creator:
Kortier, W. E. & Lyon, W. C.
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Report
250-Watt Radioisotope Thermoelectric Generator Feasibility Study. Volume 3. RTG Handling System Analysis and Design. Final Report.
Description:
No Description Available.
Date:
January 1, 1966
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Report
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.
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Report
EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies
Description:
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.
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Report
The 550$sup 0$F Notched High-Strain Behavior of Three Low-Strength Structural Steels.
Description:
No Description Available.
Date:
January 1, 1969
Creator:
Krempl, E.E.
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Report
710 high-temperature gas reactor program summary report. Volume I. Summary
Description:
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
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Report
710 high-temperature gas reactor program summary report. Volume IV. Critical experiment and reactor physics development
Description:
Reactor physical technology development was performed and its design was explained.
Date:
January 1, 1968
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Report
710 reactor program. Progress report No. 17
Description:
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 o…
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Date:
December 1, 1965
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Report
710 reactor-shield study support for manned spacecraft applications
Description:
No Description Available.
Date:
April 1, 1967
Creator:
Simpson, J.D.
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Report
710 Reactor thermoelectric space power system concepts
Description:
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.…
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Date:
September 1, 1967
Creator:
Flitner, D.P.
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Report
A 1000 HOUR TEST OF A CORROSION PRODUCT SEPARATOR UNIT IN A HAYNES ALLOY NO. 25 LOOP CONTAINING MERCURY--TEST G-16
Description:
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 successf…
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Date:
March 1, 1962
Creator:
Nejedlik, James F.
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Report
1000-Mw(e) METAL-FUELED FAST BREEDER REACTOR.
Description:
No Description Available.
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.
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Report
1000 Mwe Closed Cycle Water Reactor Study
Description:
This report has two volumes, volume 1 contains the summary and detailed description of plant design, volume 2 contains a comprehensive nuclear evaluation of the reactor core.
Date:
March 1, 1963
Creator:
Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
Item Type:
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Report
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