Corrosion of high burn-up structured UO2 fuel in presence of dissolved H-2
Artikel i vetenskaplig tidskrift, 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.

condition

product deposits

simfuel

Reducing

Irradiated

spent fuel

rim

Hydrogen

Groundwater

Corrosion

release

acidity

solubility

radionuclide

HBS

near-field hydrogen

Spent nuclear fuel

irradiation

microstructure changes

High burn-up

Författare

Patrik Fors

Chalmers, Kemi- och bioteknik, Kärnkemi

P. Carbol

European Commission Joint Research Centre, Institute for Transuranium Elements Karlsruhe

S. Van Winckel

European Commission Joint Research Centre, Institute for Transuranium Elements Karlsruhe

Kastriot Spahiu

Chalmers, Kemi- och bioteknik, Kärnkemi

Journal of Nuclear Materials

0022-3115 (ISSN)

Vol. 394 1 1-8

DOI

10.1016/j.jnucmat.2009.07.004