The gamma -radiation field from a battery of 10 MTR spent fuel elements was calculated and a special shipping cask designed to contain the 10 elements. An internal watercooled tank in the cask holds the 10 elements in the vertical position. Two external air-cooled, finned-tube heat exchangers control the water temperature. The sides of the cask open to convert the cask to a radiation source without changing the position of the elements. A unique feature of the design is a device for closing the sides of the cask by gravity in the event of accident or power failure. This provides a ''fail-safe'' safety feature. (auth)

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Measurements of thermal conductivity and electrical resistivity were continued on irradiated specimens of UO/sub 2/-clad in Zircaloy-2 with NaK as the heat-transfer medium. The creep strength of 0.15% cold-worked Zircaloy-2 is being determined at elevated temperatures. Work continued on the development of highstrength corrosion-resistant Zr alloys. Research to develop a method of sink- float density measarements to identify factors affecting irradiation-induced volume changes in graphite was continued. Single crystals of high-purity Mo are being prepared for irradiation damage studies. Casting methods are presented for Al--U alloys. Time-temperature relationships are being studied during the solidification of small cylindrical U castings to improve the quality of fabricated U fuel slugs. Methods for preparing a thin protective coating of Mo on Croloy are being investigated. Research indicates that in a binary system of UO/sub 2/-- La/sub 2/O/sub 3/ 60 wt.% La/sub 2/O/sub 3/ is required to form a stoichiometric structure after oxidation. Investigations of the hydrides of U- Zr alloy for possible use in gas-cooled reactors were continued. An irradiation- damage program on type 347 stainless steel was undertaken to study the changes in physical properties that are caused by continued exposure to a fast-neutron flux up to 3 x 10/sup 15/ nvt …

Data are presented on the creep properties of 15% coldworked Zircaloy-2 at 290, 345, and 400 deg C. The progress on the development of an isotopic- exchange fuel-element leak-detection system is summarized. A program to develop a thermal-neutron-flux monitoring system for Hanford reactors is reported. Work on the radiometric analysis of calcium in cement was continued. A surveillance program is in progress to determine the effects of fastneutron irradiation on the mechanical properties of AISI Type 347 stainless steel. A summary of corrosion results obtained on Nb, Nb-Zr, Nb-W, Nb-Mo, Nb-V, Nb-Fe, Nb-Ti, Nb-Ti-Cr, and Nb- Ti-V alloys exposed in hightemperature water and steam is presented. A study of the creep characteristics of Zircaloy-2 at elevated temperatures during exposure to a fast-neutron flux was initiated. A research program was initiated to develop an analytical technique for monitoring the oxygen concentration in largescale radioactive sodium systems. Data are presented on the corrosion behavior cf Nb-U alloys in high-temperature water after 98 days. The development of Th -U-base alloys of improved radiation stability and corrosion resistance is reported. Methods of producing cermets of 90% of theoretical density or better containing 60 to 90 vol.% ceramic fuel are being investigated. The gas-pressure- bonding …