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- W186072018 abstract "Fuel rods with zirconium alloy tube cans have been developed for large- scale atomic power stations in the USSR. The sealing of the elements is made by argon arc and seam welding of the end faces. Rods made of gintered UO/sub 2/ are used as the core of the fuel elements. The fuel elements were subjected to prolonged tests in the water loops of the reactor. Tbe main tests were carried out at the fuel element surface temperature 300 to 310 deg C and at the thermal load up to 10/sup 6/ cal/m/sup 2/hr. Some tests were carried out with the surface temperatare 350 deg C to obtain data on the margin of corrosion resistance of different zirconium alloy cans. The results of the tests have made it possible to choose the optimum fuel element design, the technology of production, and the method of disposition in the jacket. (auth)" @default.
- W186072018 created "2016-06-24" @default.
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- W186072018 date "1959-10-31" @default.
- W186072018 modified "2023-09-27" @default.
- W186072018 title "FUEL ELEMENTS FOR WATER-WATER REACTORS OF ATOMIC POWER PLANTS" @default.
- W186072018 hasPublicationYear "1959" @default.
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