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EEN-307, Irradiation of units at low temperature test

Description: EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.
Date: April 13, 1960
Creator: Guthrie, J.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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333 Building preliminary survey potential equipment improvements

Description: In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta he… more
Date: August 22, 1962
Creator: Drumheller, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EEN-333, revised getter flash procedure

Description: EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Date: June 28, 1960
Creator: Brown, W.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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710 Mockup No. 1 critical experiment. Summary data report

Description: Declassified 21 Sep 1973. A summary of the experiments associated with the three uniformly loaded core configurations related to the 710 Mockup 1 Critical Experiment Reactor is presented. These configurations mocked up specific features of the then current 710 reactor experiment design. The experimental areas included initial loading, neutron lifetime, fission ratios, reflector control methods, reactivity coefficients and power distribution measurements. A major portion of the effort was applie… more
Date: October 21, 1966
Creator: Sims, F. L.; Kunze, J. F.; Pincock, G. D. & Chase, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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710 reactor program, progress report No. 12

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design. (DCC)
Date: January 28, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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710 reactor program, progress report No. 13

Description: Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)
Date: March 31, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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… more
Date: December 1, 1965
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.… more
Date: September 1, 1967
Creator: Flitner, D.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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… more
Date: March 1, 1962
Creator: Nejedlik, James F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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