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Radiochimica Acta

International Journal for chemical aspects of nuclear science and technology

Editor-in-Chief: Qaim, Syed M.


IMPACT FACTOR 2018: 1.339

CiteScore 2018: 1.20

SCImago Journal Rank (SJR) 2018: 0.333
Source Normalized Impact per Paper (SNIP) 2018: 0.720

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2193-3405
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Volume 96, Issue 9-11

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Effects of hydrogen and bromide on the corrosion of spent nuclear fuel and γ-irradiated UO2(s) in NaCl brine

Volker Metz / A. Loida / E. Bohnert / D. Schild
  • 3 Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung, Eggenstein-Leopoldshafen, Deutschland
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/ Kathy Dardenne
Published Online: 2009-09-25 | DOI: https://doi.org/10.1524/ract.2008.1548

Abstract

Radiation induced UO2(s) corrosion is studied at elevated hydrogen pressure in NaCl brine containing traces of bromide. Release of Sr, Cs, Tc and actinides was measured in corrosion experiments with spent nuclear fuel pellets in presence of 10−2 mol H2 (kg H2O)−1, and 10−4 and 10−3 mol Br (kg H2O)−1, respectively. For comparison, depleted UO2(s) pellets were γ-irradiated in NaCl brine at 10−3 mol H2 (kg H2O)−1 and 0−10−4 mol Br (kg H2O)−1, respectively. In the γ-radiolysis experiments a significant increase in the yield of radiolytic products due to Br is observed. Both, in the γ-radiolysis experiment with Br and in that without Br, the UO2(s) sample was oxidized, and the concentration of dissolved uranium was controlled by precipitation of meta-schoepite and clarkeite. In the spent nuclear fuel corrosion experiment under H2 overpressure, aqueous concentrations of Tc and Np were in the range of solubilities of Tc(IV) and Np(IV) hydroxides, whereas measured U concentrations were between solubilities of U(VI) and U(IV) phases. The release rate of Sr was significantly increased in the presence of Br traces. Results of the complementary spent nuclear fuel corrosion and γ-radiolysis experiments allow the conclusion that Br traces reduce significantly the protective hydrogen effect with respect to the release of certain radionuclides and the yield of radiolytic products.

Keywords: Spent nuclear fuel; Radiolysis; Uranium dioxide corrosion; Hydrogen; Bromide

About the article

* Correspondence address: Forschungszentrum Karlsruhe, Institut für Nukleare Entsorgung (INE), Hermann-von Helmholtz Platz 1, 76344 Eggenstein-Leopoldshafen,


Published Online: 2009-09-25

Published in Print: 2008-11-01


Citation Information: Radiochimica Acta International journal for chemical aspects of nuclear science and technology, Volume 96, Issue 9-11, Pages 637–648, ISSN (Print) 0033-8230, DOI: https://doi.org/10.1524/ract.2008.1548.

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