Engineering and Technology

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

H. Ding, C. Gausse, et al.

Delve into the intriguing world of molten core-concrete interaction as researchers, including Hao Ding and Clémence Gausse, unveil new findings about U-Zr-O minerals and their reactive transformations. This study showcases how unique phases influence oxidation states, shedding light on the complexities of nuclear material behavior in reducing conditions.

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~3 min • Beginner • English

Index

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.

Publisher

npj Materials Degradation

Published On

Feb 02, 2022

Authors

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

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