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Grambow, B.; 二田 郁子; 柴田 淳広; 駒 義和; 宇都宮 聡*; 高見 龍*; 笛田 和希*; 大貫 敏彦*; Jegou, C.*; Laffolley, H.*; et al.
Journal of Nuclear Science and Technology, 59(1), p.1 - 24, 2022/01
被引用回数：15 パーセンタイル：71.66(Nuclear Science & Technology)Following the NPP accident, some hundred tons of nuclear fuel elements of 3 damaged nuclear reactor units were partly molten with even larger masses of steel and concrete structures, creating a big mass of corium and fuels debris. Since ten years, this heat generating mass has been cooled permanently by millions of m
of water flowing over them. Knowledge on the interaction of this solid mass with water is crucial for any decommissioning planning. Starting from analyses of the evolutions of the accident in the 3 reactor cores and associated fuel debris formations and some additional isotopic and physiochemical information of debris fragments collected in soils of Fukushima, we review the temporal evolution of the chemistry and leached radionuclide contents of the cooling water. Measured concentration ratios of the actinides and fission products in the water where compared to reported results of laboratory leaching studies with either spent nuclear fuel or simulated fuel debris under a variety of simulated environmental conditions.
仲吉 彬; Jegou, C.*; De Windt, L.*; Perrin, S.*; 鷲谷 忠博
Nuclear Engineering and Design, 360, p.110522_1 - 110522_18, 2020/04
被引用回数：14 パーセンタイル：87.95(Nuclear Science & Technology)Simulated in-vessel and ex-vessel fuel debris, fabricated in the Colima experimental facility set up in the PLINIUS platform at CEA Cadarache, were selected and leaching experiments were carried out under oxidizing conditions. In parallel, geochemical modeling was performed to better understand the experimental concentrations, pH evolutions and secondary phase's formation. Finally, the Fractional Release Rates of the (U, Zr)O
matrix for the two kinds of samples (in-vessel and ex-vessel) were found to be close to or one order of magnitude lower than that of SF under oxidizing conditions (from 10
to 10
per day), but the release processes are different.
Miro, S.*; Peuget, S.*; Tupin, M.*; Fayette, L.*; 仲吉 彬; Perrin, S.*; Jegou, C.*
no journal, ,
Micro-Raman spectroscopy is a powerful technique for analyzing nuclear materials (fuels, claddings and simulated fuel debris). For this purpose, the confocal Raman spectrometer of the Atalante facility (CEA/Marcoule), coupled to an optical microscope in a hot cell, is used to study the aging of nuclear materials in service conditions (reactor, interim storage, waste disposal) or in accidental conditions, subjected to complex scenarios of irradiation, temperature and interaction with the surrounding environment. This contribution aims to illustrate, through examples, the interest of Raman spectroscopy in the characterization of nuclear materials in a wide range of chemical composition and solicitation.
仲吉 彬; Jegou, C.*; De Windt, L.*; Perrin, S.*; Peuget, S.*; 鷲谷 忠博
no journal, ,
Simulated in-vessel and ex-vessel corium debris, fabricated in the Colima experimental facility set up in the Severe Accident PLINIUS platform at CEA Cadarache, were selected and leaching experiments were carried out under oxidizing conditions. In parallel, geochemical modeling was performed to better understand the experimental concentrations, pH evolutions and secondary phase's formation. Finally, the Fractional Release Rates of the (U, Zr)O matrix for the two kinds of samples (in-vessel and ex-vessel) were found to be close to or one order of magnitude lower than that of SF under oxidizing conditions (from 10 to 10 per day) but the release processes are different.
