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Review about the Effect of He on the Microstructure of Spent Nuclear Fuel in a Repository

Published online by Cambridge University Press:  20 February 2017

C. Ferry ,
J. Radwan  and
H. Palancher
C. Ferry*
Affiliation:
CEA, DEN, Service of fuel cycle technology development, BP 17171, 30207 Bagnols-sur-Cèze Cedex, France
J. Radwan
Affiliation:
CEA, DEN, Service for the studies of the radionuclides behavior, BP11, F-91191 Gif-sur-Yvette Cedex, France
H. Palancher
Affiliation:
CEA, DEN, Service of fuel studies and simulation, 13108 Saint Paul-Lez-Durance, France
*
*(Email: cecile.ferry@cea.fr)
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Abstract

Helium is produced in spent nuclear fuel by α-decays of actinides. After 10,000 years, the concentration of He accumulated in UO2 spent fuel is about 0.23 at.%. For direct disposal of spent nuclear fuel, consequences of helium build-up on the fuel matrix microstructure must be evaluated since it can modify the radionuclide release when water comes into contact with the spent fuel surface, after breaching of the disposal canister. An operational model has been proposed in order to evaluate the effect of helium on the microstructure of spent fuel in a repository. Based on conservative assumptions and different scenarios of bubble population, the calculated helium critical concentration, that could lead to a partial loss of integrity of the spent fuel pellet, is 0.37 at.%. However, observations on He-implanted UO2, α-doped UO2 pellets and natural analogues evidence a macroscopic damage only for He concentrations, which are more than one order of magnitude higher.

Keywords

microstructureUnuclear materials
Type
Articles
Information
MRS Advances , Volume 1 , Issue 62: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4147 - 4156
Copyright
Copyright © Materials Research Society 2017 

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