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AN AUTORADIOGRAPHIC TECHNIQUE FOR THE STUDY OF TRITIUM IN METALS AND ITS APPLICATION TO DIFFUSION IN ZIRCONIUM AT 149 to 240 C

Journal Article · · J. Nuclear Materials

Tritium was used in a novel way to obtain diffusion coefficients in zirconium at 240, 195, and 149 deg C. The specimens were prepared by electrolytically depositing a hydride layer from a tritiated water electrolyte on zirconium specimens. The 2 ml of electrolyte contained 220 curies of tritium. Details of the electrolytic cell and conditions of electrolysis are given. The tritium diffused into the specimens under closely controlled conditions of time and temperature and the distribution of tritium in the metal was then studied by autoradiographic techniques. Volume and grain boundary diffusion were studied and a number of segregation effects observed on the autoradiographs. The frequency factor for lattice diffusion of tritium in zirconium was found to be 1.53 x 10/sup -3/ cm/sup 2//ec and the activation energy 9070 plus or minus 600 cal/mole, compared with 7060 cal/mole reported for hydrogen in zirconium. The reason for the difference is discussed. The ratio of the diffusion coefficients p 4/. The significance of these and other findings is considered. (auth)

Research Organization:
International Nickel Co. of Canada, Ltd., Toronto
NSA Number:
NSA-16-030832
OSTI ID:
4782391
Journal Information:
J. Nuclear Materials, Journal Name: J. Nuclear Materials Vol. Vol: 6
Country of Publication:
Country unknown/Code not available
Language:
English