The first group of Pu--Al MTR fuel elements fubricated were rejected for excessive dimensions and blistering. The fuel element constitution and fubrication was reviewed, and a new Pu--Al ratio and revised rolling techniques were suggested. (D.E.B.)

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Daily newspaper from Cuero, Texas that includes local, state and national news along with advertising.

Daily newspaper from Sulphur Springs, Texas that includes local, state, and national news along with advertising.

Video footage from the WBAP-TV station in Fort Worth, Texas, to accompany a news story about a rooster with horns. Also includes a story about a bet that resulted in Tommy Hasty being carted down Main Street in a wheelbarrow. The segment includes a piece about a code implemented by the city council to tear down or repair slum housing.

Report presenting an investigation in the transonic pressure tunnel to determine the afterbody pressure distribution and fin loading characteristics of two configurations of the TX-21 special weapon. The only different in the two configurations was the nose contour, with one having a hemispherical-flat shape and one with a double-radius ogive-flat shape. Results regarding the pressure port, fin loads, and force measurements are provided.

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Zirconium alpha-beta alloys were found to respond to solution and aging heat treatmeats very similarly to titanium alpha-beta alloys. A zirconium-5 wt.% molybderum-2 wt.%fl tin alloy was heat treated to a L68,500-psi tensile strength and a 153,500-psi yield strength, with 11.5% elongation in 1 in. In addition, a zirconium-5 wt.% niobinm-2 wt.% tin alloy was heat treated to a 190,500-psi tensile and a 178,000-psi yield strength, with 2% elongation. The transformations that occur upon aging these alloys may be represented as follows: beta deg C was con- omega + beta /sub r/ deg C was con- alpha + beta / sub u/and alpha deg C was con- alpha + beta /sub r/. Preliminary elevated-temperature propenties were very good. The zirconium-5 wt.%fl molybderum-2 wt.%fl tin alloy solution treated at 1525 F and aged 8 hr at 1000 F was evaluated for tensile strength and 100-hr rupture life at 840 F. The tensile strengh, yield strength, and elongation were 111,000 psi, 84,500 psi, and l2%fl, respectively. The 100-hr rupture strength was about 95,000 psi. (auth)

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The conceptual design of a low cost training reactor for the instruction of physicists and engineers is covered. It is conceived as an instructional tool for a course such as that given at the Oak Ridge School of Reactor Technology. The reactor is of a modified pool type, and is designed for a maximum power level of one Mw. This arrangement will accommodate engineering experiments, shielding experiments, and critical experiments as well as being useful as a neutron and gamma source. (auth)

A conceptual design is presented for a reactor producing 3000 deg F, 400 psi steam to supply process heat for high temperature endothermic chemical reactions. Specifically, the supplying of heat to a coal hydrogenation plant is studied but other applications are possible. Such a market for nuclear heat is economically interesting because the competition is with the relatively expensive oxygen combustion of coal. It was assumed that in the present state of the art a ceramic heat source could not contain nuclear fuel in an open cycle due to the hazard of fission product leakage into the process stream. This assumption limited the high temperature heat source to the order of 10% of the total reactor power. The particular design studied was found to be not economically feasible due 10 the unusually large inventory of enriched uranium required. However, it is felt that with the suggested changes, nuclear process heat from this type of reactor oould be competitive if the excess power produced could be sold economically. (auth)

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Research in radiation effects on reactor materials is reviewed in ten papers presented by representatives of Oak Ridge National Laboratory, General Electric Company, knolls Atomic Power Laboratory, Dattelle Memorial Institute, Brookhaven Nationaal Laboratory, Argonne National Laboratory, Bettis Plant, and Atomic Power Development Associates. Separate abstracts have been prepared for each paper. (T.R.H.)

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