By H. N Friesen
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Extra info for Atmospheric Nuclear Tests in Nevada [a perspective]
BWR fuel exhibits a similar increase, however, lags about 5 MW·d/kg U behind. By 2005, peak average discharge burnup of 55 and 50 MW·d/kg U, respectively, should be achieved. Burnup increase has been and will be achieved by increasing the fuel’s enrichment and has to be accompanied by improved material properties such as the corrosion resistance of the cladding. Burnup development, however, is generally limited by the enrichment licenced by the authorities for handling unirradiated fuel during manufacturing or storage at the nuclear power plants.
3 % Pu/U + Pu), (4) PWR and BWR rod designs and operating conditions, (5) Wet conditions of storage for most rods with some fuel pieces stored in dry conditions. The programme is intended to examine the cladding with regard to outer corrosion, mechanical properties and deformation under inner pressure, and the fuel with regard to integrity (microstructure, swelling) and chemical stability. Rod examinations will provide the inner gas pressure and composition. Special attention will be given to MOX fuel by performing additional helium release tests.
However, systematic studies comparable to those available or underway for Zircaloy materials are desirable and recommended, 29 (3) Advanced cladding materials are of increasing commercial importance for PWR fuel. From the existing inpile experience no dramatic consequences are expected on long term storage. However, systematic studies comparable to those available or underway for Zircaloy materials are desirable and recommended, (4) Today the long term storage experience with Russian Zr1Nb material (E 110) is based on very long wet storage experience.