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DEMONSTRATION DISPOSAL OF HIGH-LEVEL RADIOACTIVE SOLIDS IN LYONS, KANSAS, SALT MINE: BACKGROUND AND PRELIMINARY DESIGN OF EXPERIMENTAL ASPECTS

Description: A demonstration of the disposal of high-level radioactive waste solids to be carried out in a salt mine at Lyons, Kansas, will have as its objectives: (1) the demonstration of required waste-handling equipment and techniques, (2) the determination of the stability of salt under the influence of heat and radiation, and (3) the collection of information on creep and plastic flow of salt which is needed for the design of an actual disposal facility. As presently conceived, 14 irradiated fuel assem… more
Date: January 10, 1964
Creator: Bradshaw, R. L.; Perona, J. J. & Blomeke, J. O.
Item Type: Refine your search to only Report
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Design Considerations Of Ultrahigh Vacuum Systems For Metallurgical Applications

Description: Under the stimulus of electronic materials development - particularly thin-film studies - and the need for space environmental simulation chambers, a very rapid increase in the availability of industrial-sized vacuum components and systems operable in the ultrahigh vacuum range has taken place in the last three years. It is the purpose of this paper to explore the design considerations of ultrahigh vacuum systems for metallurgical applications.
Date: June 10, 1964
Creator: Batzer, Thomas H. & Bunshah, R. F. (Rointan Framroze)
Item Type: Refine your search to only Report
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Design test request No. 1263 K Reactor graphite key and VSR channel sleeve test

Description: The objectives of this test were: (1) Determine the coefficient of friction between two adjacent layers of K Reactor graphite at room temperature. (2) Determine the average load required to cause failure of an unirradiated K Reactor side reflector bar, when subjected to tensile loading applied through the reflector keys. (3) Determine the average load at failure and the average deflection at failure of a single VSR channel key when loaded in keyways with clearances equal to those used in origin… more
Date: December 10, 1964
Creator: Kempf, F. J.
Item Type: Refine your search to only Report
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Development of Plutonium-Bearing Fuel Materials. Monthly Progress Letter for February 1964

Description: During this period, plutonium wire was extruded and three crystal growing tests were performed in the modified Andrade apparatus. In addition, continued effort has been placed on the fabrication of the high burnup irradiation test specimens, on additional UO2-PuO2 sintering studies and on oxygen diffusion and thermal expansivity measurements.
Date: March 10, 1964
Creator: Puechl, K. H.
Item Type: Refine your search to only Report
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Interim normal limits DR reactor

Description: As specified in PITA IP-26-I, a test has been conducted at DR reactor to find the amount of nonpressure sensitive air entering the reactor, and gain other information on the reactor gas system. The purpose of this document is to place in effect interim normal gas purity limits and define assuredly positive gas system pressure based on the results of this test.
Date: February 10, 1964
Creator: George, D. K.
Item Type: Refine your search to only Report
open access

Neptunium-237 production forecasts, IPD 1964--73

Description: Neptunium-237 production has been-calculated according to the equations documented in Reference 1 for use in 1964-AEC study. cases. The assumptions made in the forecasts are as follows: Only the 947 stream is recycled. The blend enrichment for the recycle maternal is 1.2 per cent for F-Y 64 and 65. For FY 66 -73, a blend enrichment of 1.4 per cent is assumed which is better value according to the optimization model of C. W. Showalter. The 947 stream recycle time is two years. In cases A and B w… more
Date: July 10, 1964
Creator: Nilson, R.
Item Type: Refine your search to only Report
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