TY - JOUR
T1 - Structure, stability, and actinide leaching of simulated nuclear fuel debris synthesized from UO2, Zr, and stainless-steel
AU - Kirishima, Akira
AU - Akiyama, Daisuke
AU - Kumagai, Yuta
AU - Kusaka, Ryoji
AU - Nakada, Masami
AU - Watanabe, Masayuki
AU - Sasaki, Takayuki
AU - Sato, Nobuaki
N1 - Funding Information:
This study was supported by the JAEA Nuclear Energy S&T and Human Resource Development Project through concentrated wisdom [grant number JPJA18P18071886]. A part of this study was supported by the “Dynamic Alliance for Open Innovation Bridging Human, Environment and Materials” of the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT). A.K. would like to thank Ms. Yumiko Watanabe (Tohoku University) for her assistance with the experiments and manuscript preparation. We would like to thank Editage ( www.editage.com ) for English language editing.
Publisher Copyright:
© 2022
PY - 2022/8/15
Y1 - 2022/8/15
N2 - To evaluate the chemical structure and stability of nuclear fuel debris comprising UO2, Zr, and stainless-steel (SUS) generated during the Fukushima Daiichi Nuclear Power Plant accident in Japan in 2011, the simulated debris of a UO2–SUS–Zr system and those of other fundamental-component-containing systems were synthesized and characterized. The simulated debris was synthesized by heat treatment at 1600 °C under inert (Ar) or oxidative (Ar + 2% O2) atmospheres for 1–12 h. 237Np and 241Am tracers were doped for leaching tests from the simulated debris. The simulated debris was characterized using X-ray diffraction, scanning electron microscopy–energy-dispersive X-ray spectroscopy, Raman spectroscopy, and Mössbauer spectroscopy, and the results revealed that the major uranium phase of the UO2–SUS–Zr debris comprised a Zr(IV)-and-Fe(II)-containing UIVO2 solid-solution, regardless of the treatment conditions. The results of a long-term immersion test of the simulated debris in pure water and seawater revealed that the macroscale crystal structure of the simulated debris was chemically durable under wet conditions for at least a year. Furthermore, the leaching test results indicated that the leaching ratios of U, Np, and Am from the UO2–SUS–Zr debris were small and lower than 0.08% for all the experiments in this study.
AB - To evaluate the chemical structure and stability of nuclear fuel debris comprising UO2, Zr, and stainless-steel (SUS) generated during the Fukushima Daiichi Nuclear Power Plant accident in Japan in 2011, the simulated debris of a UO2–SUS–Zr system and those of other fundamental-component-containing systems were synthesized and characterized. The simulated debris was synthesized by heat treatment at 1600 °C under inert (Ar) or oxidative (Ar + 2% O2) atmospheres for 1–12 h. 237Np and 241Am tracers were doped for leaching tests from the simulated debris. The simulated debris was characterized using X-ray diffraction, scanning electron microscopy–energy-dispersive X-ray spectroscopy, Raman spectroscopy, and Mössbauer spectroscopy, and the results revealed that the major uranium phase of the UO2–SUS–Zr debris comprised a Zr(IV)-and-Fe(II)-containing UIVO2 solid-solution, regardless of the treatment conditions. The results of a long-term immersion test of the simulated debris in pure water and seawater revealed that the macroscale crystal structure of the simulated debris was chemically durable under wet conditions for at least a year. Furthermore, the leaching test results indicated that the leaching ratios of U, Np, and Am from the UO2–SUS–Zr debris were small and lower than 0.08% for all the experiments in this study.
KW - Actinides
KW - Alloys
KW - Chemical stability
KW - Fuel debris
KW - Fukushima Daiichi nuclear power plant accident
KW - Oxides
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U2 - 10.1016/j.jnucmat.2022.153842
DO - 10.1016/j.jnucmat.2022.153842
M3 - Article
AN - SCOPUS:85131689637
SN - 0022-3115
VL - 567
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 153842
ER -