English (United Kingdom)

https://curated-unify.zendy.io/wp-json/zendy-region/v1/featured_content/oa?rat=en

https://curated-unify.zendy.io/wp-json/zendy-region/v1/highlighted_journal/

Zendy Open

Presents the pdf analysis as premium feature

PDF Analysis

Insights

Presents the summarisation as premium feature

Summarisation

Presents the keyphrase highlighting as premium feature

Keyphrase Highlighting

Presents the zaia usage as premium feature

ZAIA

Zendy Tools

Zendy Plus

Presents the access of premium content as premium feature

Premium Content

Radiation induced UO 2 (s) corrosion is studied at elevatedhydrogen pressure in NaCl brine containing traces of bromide. Release ofSr, Cs, Tc and actinides was measured in corrosion experiments withspent nuclear fuel pellets in presence of 10 −2  molH 2  (kg H 2 O) −1 , and 10 −4and 10 −3  mol Br −  (kgH 2 O) −1 , respectively. For comparison, depletedUO 2 (s) pellets were γ-irradiated in NaCl brine at10 −3  mol H 2  (kg H 2 O) −1and 0−10 −4  mol Br −  (kg H 2 O) −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 UO 2 (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 H 2  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.

Effects of hydrogen and bromide on the corrosion of spent nuclear fuel and γ -irradiated UO 2 (s) in NaCl brine