npj Materials Degradation (Feb 2022)

Chemical characterisation of degraded nuclear fuel analogues simulating the Fukushima Daiichi nuclear accident

  • Hao Ding,
  • Clémence Gausse,
  • Malin C. Dixon Wilkins,
  • Lucy M. Mottram,
  • Martin C. Stennett,
  • Daniel Grolimund,
  • Ryan Tappero,
  • Sarah Nicholas,
  • Shikuan Sun,
  • Tomooki Shiba,
  • C. Paraskevoulakos,
  • Neil C. Hyatt,
  • Claire L. Corkhill

DOI
https://doi.org/10.1038/s41529-022-00219-3
Journal volume & issue
Vol. 6, no. 1
pp. 1 – 13

Abstract

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Abstract The Fukushima Daiichi accident generated degraded nuclear fuel material, mixed with other reactor components, known as molten core-concrete interaction (MCCI) material. Simulant MCCI material was synthesised, excluding highly radioactive fission products, containing depleted U, and incorporating Ce as a surrogate for Pu. Multi-modal µ-focus X-ray analysis revealed the presence of the expected suite of U-Zr-O containing minerals, in addition to crystalline silicate phases CaSiO3, SiO2-cristobalite and Ce-bearing percleveite, (Ce,Nd)2Si2O7. The formation of perclevite resulted from reaction between the U-Zr-O-depleted Ce-Nd-O melt and the silicate (SiO2) melt. It was determined that the majority of U was present as U4+, whereas Ce was observed to be present as Ce3+, consistent with the highly reducing synthesis conditions. A range of Fe-containing phases characterised by different average oxidation states were identified, and it is hypothesised that their formation induced heterogeneity in the local oxygen potential, influencing the oxidation state of Ce.