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Yaohiro Inagaki Last modified date：2023.06.22

Associate Professor / Quantum Sciences of Materials
Department of Applied Quantum Physics and Nuclear Engineering
Faculty of Engineering


Graduate School
Graduate School of Engineering
Department of Applied Quantum Physics and Nuclear Engineering
Graduate School of Engineering
Undergraduate School
School of Engineering
Department of Energy Science and Engineering
School of Engineering
Other Organization
Research Center for Environmental Engineering


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Homepage
https://kyushu-u.pure.elsevier.com/en/persons/yaohiro-inagaki
　Reseacher Profiling Tool　Kyushu University Pure
Phone
092-802-3493
Fax
092-802-3501
Academic Degree
Doctor of Engineering
Country of degree conferring institution (Overseas)
No
Field of Specialization
Radioactive Waste Management, Nuclear Waste Glass, Nuclear Fuel Cycle
Total Priod of education and research career in the foreign country
00years00months
Outline Activities
Research on Radioactive Waste Management, Developing the Scientific Basis and Safety Assessment Methods, Advanced Nuclear Fuel Cycle system, the related education on fundamentals.
Research
Research Interests
  • Radioactive waste management, Total performance of advanced nuclear fuel cycle development　
    keyword : Radioactive waste, waste form, waste glass, geological disposal, performance assessment, advanced nuclear fuel cycle
    1988.08～2021.03.
Academic Activities
Reports
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Papers
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1. Yaohiro Inagaki, Micro-channel as a new tool to investigate glass dissolution kinetics, Procedia Materials Science, 7, 172 -178, 2014.12, A reliable modeling of the long-term dissolution of HLW glass requires sufficient evaluation of the glass dissolution kinetics
including a sound understandings of reaction mechanism. For the evaluation of glass dissolution kinetics, we need much more
data on the glass dissolution rate measured precisely, consistently and systematically under various well-constrained test
conditions. The current standard test methods, unfortunately, cannot provide enough data for the kinetic evaluation. Therefore,
we should improve or develop the test methods to provide precise and consitent data for the kinetic evaluation. In the present
paper, therefore, major standard test methods currently applied to the measurement of glass dissolution are summarized with
their advantages and disadvantages, and some newly developed test methods are introduced. In addition, problems to be solved
are discussed to advance the kinetic evaluation..
2. Yaohiro Inagaki, Hikaru Makigaki, Kazuya Idemitsu, Tatsumi Arima, Sei-IchiroMitsui and Kenji Noshita, Initial dissolution rate of a Japanese simulated high-level waste glass P0798 as a function of pH and temperature measured by using micro-channel flow-through test method, Journal of Nuclear Science and Technology, Volume 49, No. 4, pp. 438–449, 2012.04, Aqueous dissolution tests were performed for a Japanese type of simulated high-level waste (HLW) glass
P0798 by using a newly developed test method of micro-channel flow-through (MCFT) method, and the
initial dissolution rate of glass matrix, r0, was measured as a function of solution pH (3–11) and
temperature (25–908C) precisely and consistently for systematic evaluation of the dissolution kinetics. The
MCFT method using a micro-channel reactor with a coupon shaped glass specimen has the following
features to provide precise and consistent data on the glass dissolution rate: (1) any controlled constant
solution condition can be provided over the test duration; (2) the glass surface area actually reacting with
solution can be determined accurately; and (3) direct and totally quantitative analyses of the reacted glass
surface can be performed for confirming consistency of the test results. The present test results indicated
that the r0 shows a ‘‘V-shaped’’ pHdependence with aminimumat around pH6 at 258C, but it changes to a
‘‘U-shaped’’ one with a flat bottom at neutral pH at elevated temperatures of up to 908C. The present
results also indicated that the r0 increases with temperature according to an Arrhenius law at any pH, and
the apparent activation energy evaluated from Arrhenius relation increases with pH from 54 kJ/mol at pH
3 to 76 kJ/mol at pH 10, which suggests that the dissolution mechanism changes depending on pH..
3. Y,Inagaki, S.Mitsui, H.Makigaki, K.Idemitsu, T.Arima, T.Banba, K.Noshita, Measurement of HLW glass dissolution/alteration kinetics by using micro-reactor flow-through test method, Scientific Basis for Nuclear Waste Management XXXIII (Mat.Res.Soc.Symp.Proc.1193), 219, 2009.12.
4. Yaohiro INAGAKI, Tomohiko IWASAKI, Seichi SATO, Toshiaki OHE, Kazuyuki KATO, Seishi TORIKAI, Yuichi NIIBORI, Shinya NAGASAKI, Kazumi KITAYAMA, LWR High Burn-Up Operation and MOX Introduction; Fuel Cycle Performance from the Viewpoint of Waste Management, Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.46, No.7, pp.677-689, Vol.46, No.7, pp.677-689, 2009.07.
5. Yaohiro INAGAKI, Toshitaka IMAMURA , Kazuya IDEMITSU , Tatsumi ARIMA,Osamu KATO , Tsutomu NISHIMURA and Hidekazu ASANO, Aqueous Dissolution of Silver Iodide and Associated Iodine Release under Reducing Conditions with FeCl2 Solution , Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 45, No. 9, p. 859–866 (2008) , Vol. 45, No. 9, p. 859–866 (2008) , 2008.09.
6. Y.Inagaki, T.Saruwatari, K.Idemitsu, T.Arima, A.Shinkai, H.Yoshikawa, M.Yui, Temperature Dependence of Long-Term Alteration Rate for Aqueous Alteration of P0798 Simulated Waste Glass under Smectite Forming Conditions, Scientific Basis for Nuclear Waste Management (Mat. Res. Soc. Symp. Proceedings Vol.932), pp.321-328, 2006.08.
Presentations
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1. A new type of flow-through test method using micro-reactor was developed and applied to measurement of the dissolution/alteration kinetics for a Japanese type of simulated HLW glass, P0798..
Membership in Academic Society
  • Material Research Society
  • The American Ceramic Society
Awards
  • "Burning of MOX fuels in LWRs; fuel history effects on thermal properties of hull and end piece wastes and the repository performance", F.Hirano, Y.Inagaki, T.Iwasaki, et al., Journal of Nuclear Science and Technology, Vol.49，No.3(2012）p.310～319


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