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.

solubility

acidity

radionuclide

HBS

microstructure changes

Spent nuclear fuel

rim

Corrosion

near-field hydrogen

condition

spent fuel

Groundwater

Irradiated

simfuel

release

Reducing

product deposits

Hydrogen

High burn-up

irradiation

Författare

Patrik Fors

Chalmers, Kemi- och bioteknik, Kärnkemi

P. Carbol

Gemensamma forskningscentrumet (JRC), Europeiska kommissionen

S. Van Winckel

Gemensamma forskningscentrumet (JRC), Europeiska kommissionen

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

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Senast uppdaterat

2020-09-03