Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2
Journal article, 2009

The influence of high burn-up structured material on UO2 corrosion has been studied in an autoclave experiment. The experiment was conducted on spent fuel fragments with an average burn-up of 67 GWd/tHM. They were corroded in a simplified groundwater containing 33 mM dissolved H-2 for 502 days. All redox sensitive elements were reduced. The reduction continued until a steady-state concentration was reached in the leachate for U at 1.5 x 10(-10) M and for Pu at 7 x 10(-11) M. The instant release of Cs during the first 7 days was determined to 3.4% of the total inventory. However, the Cs release stopped after release of 3.5%. It was shown that the high burn-up structure did not enhance fuel corrosion. (C) 2009 Elsevier B.V. All rights reserved.

release

spent fuel

condition

radionuclide

High burn-up

rim

acidity

simfuel

solubility

near-field hydrogen

Hydrogen

Groundwater

product deposits

HBS

Spent nuclear fuel

microstructure changes

Corrosion

Reducing

Irradiated

irradiation

Author

Patrik Fors

Chalmers, Chemical and Biological Engineering, Nuclear Chemistry

P. Carbol

European Commission (EC)

S. Van Winckel

European Commission (EC)

Kastriot Spahiu

Chalmers, Chemical and Biological Engineering, Nuclear Chemistry

Journal of Nuclear Materials

0022-3115 (ISSN)

Vol. 394 1 1-8

DOI

10.1016/j.jnucmat.2009.07.004

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3/10/2025