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Overview of the French research on the evolution of spent fuel rod after discharge from the reactor

Published online by Cambridge University Press:  15 February 2011

C. Ferry
Affiliation:
CEA-Saclay, Nuclear Energy Division, 91191 Gif-sur-Yvette cedex, France
C. Cappelaere
Affiliation:
CEA-Saclay, Nuclear Energy Division, 91191 Gif-sur-Yvette cedex, France
C. Jegou
Affiliation:
CEA-Marcoule, Nuclear Energy Division, BP 17171, 30207 Bagnols sur Ceze, France
J.P. Piron
Affiliation:
CEA-Cadarache, Nuclear Energy Division, 13108 Saint-Paul lez Durance cedex, France
M. Firon
Affiliation:
CEA-Saclay, Nuclear Energy Division, 91191 Gif-sur-Yvette cedex, France
A. Ambard
Affiliation:
EDF, R&D division, les Renardieres, F-77818 Moret-sur-Loing Cedex, France
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Abstract

Since 2006, French research on spent fuel has focused on the main issues related to transport and extended in-pool storage of spent fuel assembly. Studies on creep behaviour of irradiated cladding have resulted in a new creep model which is valid over a wide domain of temperature, internal pressure and time. Under nominal conditions, no evolution of the spent fuel rod is expected during in-pool storage. In case of defective fuel rods in the storage pool, the consequences of fuel alteration on the initial defect of the cladding depend on the matrix alteration rate and nature of the secondary phases formed. Considering the optional scenario of direct disposal, the long-term behaviour of the spent fuel is investigated focusing on helium consequences before water contact on the one hand and on the influence of repository conditions on matrix alteration on the other hand. The aim of the on-going studies is to improve the safety margins initially introduced in the radionuclide source term models.

Type
Research Article
Copyright
Copyright © Materials Research Society 2009

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