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BRAZING OF CERAMICS. Progress Report

Description: Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover pla… more
Date: November 1, 1962
Creator: Fox, C.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PROCESSES FOR RECOVERY OF URANIUM AND THORIUM FROM GRAPHITE-BASE FUEL ELEMENTS. PART II

Description: Laboratory-scale tests on methods for recovering uranium and thorium from graphite-base reactor fuel elements are reported. The 90% HNO/sub 3/ process, which involves simultaneous disintegration and leaching in 21 M HNO/sub 3/, is applicable to all fuel elenments which do not contain coated fuel particles. Leaching of irradiated (0.001% burnup) fuels containing 3 and 12% uranlum recovered approximates 99.3 and 99.9%, respectively, of the uranium in two 4-hr leaches with boiling acid. The graphi… more
Date: November 30, 1961
Creator: Ferris, L.M.; Kibbey, A.H. & Bradley, M.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uranium Recovery, Uranium Geochemistry, Thermoluminescence and Related Studies. Final Report

Description: The recovery of urantum at the mine with portable equipment was shown to be feasible, using a process which involves grinding the ore, leaching with nitric acid, extracting with tributyl phosphate and kerosene, and precipitation with ammonia gas. The system is more expensive than a stationary plant but couid be used in an emergency or in difficulty accessible locations. The distribution of uranium was studied in various geographical locations and in several different materials including limesto… more
Date: November 1, 1957
Creator: Daniels, F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SINTERED ALUMINA AS A PUMP BEARING AND JOURNAL MATERIAL

Description: Design criteria and operating experience with the aluminum oxide bearing and journal combination as installed in canned rotor pumps in in-pile loops are described. No pump failures occurred in 8 pumps with A1/sub 2/0/sub 3/ bearings over a cumulative period of l0,000 hours due to wear or corrosion. Five failures due to slippage and/or electrical breakdown of the stator insulation are reported. (T.R.H.)
Date: November 26, 1957
Creator: Savage, H.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Processing Technology Quarterly Progress Report, April-June 1961

Description: The Idaho Chemical Processing Plant did not operate on fuel recovery during this period, due to extensive renovation and modiflcation of facilities. Potasslum fluoride was found to be an undesirable additive to the barium precipitating agent used in formation of barium fluozirconate, because of precipitation and loss of uranium, although essentially complete precipitation of zirconium was achieved. Addition of hydrofluoric acid with barium precipitant, to achieve a fluoride/zirconium mole ratio… more
Date: November 10, 1961
Creator: Bower, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE COMPATIBILITY OF Al$sub 2$O$sub 3$-, BeO-, AND METAL- COATED UO$sub 2$ PARTICLES WITH GRAPHITE AND COKE

Description: The compatibility of carbon and graphite matrices with UO/sub 2/ particles coated with Al/sub 2/O/sub 3/, BeO, nickel, niobium, and nickel- chromium alloy was investigated at several temperatures up to 3OOO deg F in flowing helium. Two different carbonaceous fillers and binders were used. As expected, the 2 to 8- mu metal coatings were badly damaged by reaction with carbon at temperatures as low as 17OO deg F. Both oxide coatings were completely destroyed after 6 hr at 3000 deg F. Considerable … more
Date: November 28, 1960
Creator: Gerds, A.F. & Smalley, A.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. PHASE I. Progress Report for May 1, 1959 to October 31, 1959

Description: Numerous types of high temperature ceramic fuel elements for the Pebble Bed Reactor are being evaluated. Specimens are 1 1/2 in. diameter uranium graphite spheres with external coatings such as silicon carbide or pyrolytically deposited high density graphite and fuel particle coatings such as alumina. Low fission product leakage rates at high temperatures have been observed for some of these coatings. High-level irradiation has given no visible evidence of radiation damage to either the silicon… more
Date: November 30, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP Programs. Quarterly Progress Report No. 1 for October 22-December 31, 1959

Description: An analysis was made of the SNAP III generator to determine the cause of failure, and the test specifications were revised in line with the findings. During calibration and demonstration runs with the SNAP III-A generator, a leak developed in the valving mechanism of the variable heatdump system. An examination disclosed that the valve was not satisfactory, so the generator was returned to the manufacturer for repair. A description is given of the generator, along with a performance evaluation … more
Date: November 1, 1960
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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