TY - JOUR
T1 - Study on the chemical structure and actinide leaching of MCCI debris
AU - Kirishima, Akira
AU - Nagatomo, Akito
AU - Akiyama, Daisuke
AU - Sasaki, Takayuki
AU - Sato, Nobuaki
N1 - Funding Information:
This work was supported by JSPS KAKENHI (grant number 16H02447 ). A part of this work was performed under the Research Program for CORE lab of “Dynamic Alliance for Open Innovation Bridging Human, Environment and Materials” in “Network Joint Research Center for Materials and Devices.”
Publisher Copyright:
© 2019 Elsevier B.V.
PY - 2019/12/15
Y1 - 2019/12/15
N2 - To understand the chemical structure and stability of molten core-concrete interaction (MCCI) debris generated by the Fukushima Daiichi nuclear power plant accident in Japan in 2011, simulated MCCI debris consisting of the U–Zr–Ca–Si–O system and other simpler systems were synthesized and characterized. 237Np and 241Am tracers were doped for the leaching tests of these elements and U from the simulated debris. The MCCI debris were synthesized by heat treatment at 1200 °C or 1600 °C, in reductive (Ar + 10% H2) or oxidative (Ar + 2% O2) atmospheres. Subsequently, the debris were used for actinide leaching tests with water. Zr and Ca formed a solid-solution with the UO2 matrix, such as (ZryU1-y)O2+x, (CayU1-y)O2+x, and (CazZryU1-y-z)O2, which stabilized the matrix and suppressed actinide leaching from the simulated debris. On the other hand, the cement components (CaO and SiO2) in the debris formed a glass-like coating on the debris, which also remarkably suppressed the leaching of actinides.
AB - To understand the chemical structure and stability of molten core-concrete interaction (MCCI) debris generated by the Fukushima Daiichi nuclear power plant accident in Japan in 2011, simulated MCCI debris consisting of the U–Zr–Ca–Si–O system and other simpler systems were synthesized and characterized. 237Np and 241Am tracers were doped for the leaching tests of these elements and U from the simulated debris. The MCCI debris were synthesized by heat treatment at 1200 °C or 1600 °C, in reductive (Ar + 10% H2) or oxidative (Ar + 2% O2) atmospheres. Subsequently, the debris were used for actinide leaching tests with water. Zr and Ca formed a solid-solution with the UO2 matrix, such as (ZryU1-y)O2+x, (CayU1-y)O2+x, and (CazZryU1-y-z)O2, which stabilized the matrix and suppressed actinide leaching from the simulated debris. On the other hand, the cement components (CaO and SiO2) in the debris formed a glass-like coating on the debris, which also remarkably suppressed the leaching of actinides.
KW - Actinides
KW - Fuel debris
KW - Fukushima NPP
KW - Leaching
KW - Molten core-concrete interaction
KW - Severe accident
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U2 - 10.1016/j.jnucmat.2019.151795
DO - 10.1016/j.jnucmat.2019.151795
M3 - Article
AN - SCOPUS:85072193610
SN - 0022-3115
VL - 527
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
M1 - 151795
ER -