Community Research and Development Information Service - CORDIS


One of the major problems that face the designers and users of nuclear power plants is the demonstration of the cladding integrity (the Zircaloy clad that contains the fuel pellets). The present paper recalls the effects of irradiation on the fuel pellet mechanical behaviour, then the microindentation device is presented, as well as the principles that underline its use. Finally, the way the experimental results will be used to determine the mechanical behaviour of the fuel pellet under irradiation will be pointed out.

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Authors: BARON D, EDF Etudes et Recherches, Ecuelles (FR) JRC Karlsruhe (DE);LECLERCQ S, EDF Etudes et Recherches, Ecuelles (FR) JRC Karlsruhe (DE);SPINO J, EDF Etudes et Recherches, Clamart (FR);TAHERI S,
Bibliographic Reference: Paper presented: IAEA Technical Committee Meeting on Advances in Pellet Technology for Improved Performance at High Burnup, Tokyo (JP), October 28-November 1, 1996
Availability: Available from (1) as Paper EN 40288 ORA
Record Number: 199710208 / Last updated on: 1997-04-01
Original language: en
Available languages: en