Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO 2 /water interface

X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide. Single crystal thin films of UO 2 were exposed to an intense X-ray beam at a synchrotron source in the presence of water, in order to simultaneously provide radiation fields required to split the water into highly...

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Veröffentlicht in:Faraday discussions 2015, Vol.180, p.301-311
Hauptverfasser: Springell, Ross, Rennie, Sophie, Costelle, Leila, Darnbrough, James, Stitt, Camilla, Cocklin, Elizabeth, Lucas, Chris, Burrows, Robert, Sims, Howard, Wermeille, Didier, Rawle, Jonathan, Nicklin, Chris, Nuttall, William, Scott, Thomas, Lander, Gerard
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container_start_page 301
container_title Faraday discussions
container_volume 180
creator Springell, Ross
Rennie, Sophie
Costelle, Leila
Darnbrough, James
Stitt, Camilla
Cocklin, Elizabeth
Lucas, Chris
Burrows, Robert
Sims, Howard
Wermeille, Didier
Rawle, Jonathan
Nicklin, Chris
Nuttall, William
Scott, Thomas
Lander, Gerard
description X-ray diffraction has been used to probe the radiolytic corrosion of uranium dioxide. Single crystal thin films of UO 2 were exposed to an intense X-ray beam at a synchrotron source in the presence of water, in order to simultaneously provide radiation fields required to split the water into highly oxidising radiolytic products, and to probe the crystal structure and composition of the UO 2 layer, and the morphology of the UO 2 /water interface. By modeling the electron density, surface roughness and layer thickness, we have been able to reproduce the observed reflectivity and diffraction profiles and detect changes in oxide composition and rate of dissolution at the Ångström level, over a timescale of several minutes. A finite element calculation of the highly oxidising hydrogen peroxide product suggests that a more complex surface interaction than simple reaction with H 2 O 2 is responsible for an enhancement in the corrosion rate directly at the interface of water and UO 2 , and this may impact on models of long-term storage of spent nuclear fuel.
doi_str_mv 10.1039/C4FD00254G
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title Water corrosion of spent nuclear fuel: radiolysis driven dissolution at the UO 2 /water interface
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