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tatsumi arima Last modified date：2024.04.16

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


Papers
1. Romain Vauchy, Taku Matsumoto, Shun Hirooka, Hiroki Uno, Tetsuya Tamura, Tatsumi Arima, Yaohiro Inagaki, Kazuya Idemitsu, Hiroki Nakamura, Masahiko Machida, Tatsutoshi Murakami, Masato Kato, Uranium–plutonium–americium cation interdiffusion in polycrystalline (U,Pu,Am)O2±x mixed oxides, Journal of Nuclear Materials, 10.1016/j.jnucmat.2023.154786, 588, 154786, 2024.01.
2. Tetsuo Fukasawa, Akihiro Suzuki, Yoichi Endo, Yaohiro Inagaki, Tatsumi Arima, Yusa Muroya, Keita Endo, Daisuke Watanabe, Tatsuo Matsumura, Katsunori Ishii, Junichi Yamashita, Flexible waste management system for the future application of MA P&T technology to the current hight-level liquid waste, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 10.1080/00223131.2023.2226673, 61, 3, 303-317, 2024.06.
3. K. Morita, W. Liu, T. Arima, Y. Arita, I. Sato, H. Matsuura, Y. Sekio, H. Sagara, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications, Journal of Nuclear Engineering and Radiation Science, 10.1115/1.4056854, 9, 4, 041102-1-041102-9, 2023.10.
4. K. Idemitsu, Y. Inagaki, T. Arima, Long-term diffusion of neptunium and other elements in compacted bentonite reveals filtration, MRS Advances, 10.1557/s43580-023-00501-9, 6, 2023.06.
5. H. Sakasegawa, M. Nomura, K. Sawayama, T. Nakayama, Y. Yaita, H. Yonekawa, N. Kobayashi, T. Arima, T. Hiyama, E. Murata, Liquid decontamination using acidic electrolyzed water for various uranium-contaminated steel surfaces in dismantled centrifuge, Progress in Nuclear Energy, 10.1016/j.pnucene.2022.104396, 153, 104396, 2022.11.
6. K. Idemitsu, H. Arimitsu, M. Hirakawa, K. Yoshida, Y. Inagaki, T. Arima, Effect of carbonate on the migration behavior of neptunium in compacted bentonite, MRS Advances, 10.1557/s43580-022-00210-9, 6, 140-143, 2022.03.
7. M.V. Pham, T. Arima, Y. Inagaki, K. Idemitsu, D. Akiyama, T. Nagai, Y. Okamoto, Crystal structure of U1-yLnyO2-x (Ln = Gd, Er) solid solution, Journal of Nuclear Materials, https://doi.org/10.1016/j.jnucmat.2021.153189, 556, 153189, 2021.12.
8. K. Idemitsu, K. Yoshida, Y. Inagaki, T. Arima, Speciation by XANES of copper migrated into compacted bentonite using electromigration techniques, MRS Advances, https://doi.org/10.1557/s43580-021-00026-z, 6, 80-83, 2021.02.
9. M.V. Pham, T. Arima, Y. Inagaki, K. Idemitsu, Evaluation of Structural and Thermal Properties of Ce1-yGdyO2-x Solid Solution, International Journal of Thermophysics, https://doi.org/10.1007/s10765-020-02689-6, 41, 8, 111, 2020.08.
10. M.V. Pham, T. Arima, Y. Inagaki, K. Idemitsu, Evaluation of mechanical properties of (Ce,Gd)O2-x as surrogate for (U,Gd)O2-x solid solutions, International Conference on Nuclear Engineering, 2019.05.
11. T. Arima, J. Miyachi, M.V. Pham, Y. Inagaki, K. Idemitsu, Evaluation of melting behavior in the system UO2-ZrO2: Molecular dynamics simulation, International Conference on Nuclear Engineering, 2019.05.
12. K. Idemitsu, R. Yamada, M. Hirakawa, Y. Kakoi, H. Arimitsu, Y. Inagaki, T. Arima, Effect of Carbonate on the Migration Behavior of Strontium in Compacted Bentonite, MRS Advances, 4, 1021-1027, 2019.04.
13. K. Idemitsu, K. Fujii, N. Maeda, Y. Kakoi, N. Okubo, Y. Inagaki, T. Arima, Effect of Carbonate on the Migration Behavior of Lanthanides in Compacted Bentonite, MRS Advances, ３, 1155-1160, 2018.04.
14. R. Kimura, Y. Inagaki, K. Idemitsu, T. Arima, Vitrification processes of simulated cesium sorbing zeolite waste, Progress in Nuclear Energy, 108, 497-502, 2018.04.
15. H. Sakuma, Y. Tachi, K. Yotsuji, S. Suehara, T. Arima, N. Fujii, K. Kawamura, A. Honda, Stability of Montmorillonite Edge Faces Studied Using Firstprinciples Calculations, Clay and Clay Minerals, 65, 252-272, 2017.08.
16. Kazuya Idemitsu, Noriya Okubo, Yaohiro Inagaki, Tatsumi Arima, Daisuke Akiyama, Kenji Konashi, Makoto Watanabe, Plutonium Migration in Compacted Bentonite with Iron Corrosion for 15 Years, MRS Advances, 10.1557/adv.2017.12, 2, 12, 693-698, 2017.01, In disposal of high-level radioactive waste, carbon steel overpack will be corroded after closure of the repository, creating a reducing, low-pH environment around the repository. A plutonium diffusion experiment was performed over 15 years with Kunigel V1, which is a typical Japanese bentonite that contains about 50% montmorillonite, in contact with an iron coupon. A tracer solution (10 L) containing 1 kBq of 238Pu was applied at the interface between the iron coupon and compacted bentonite that was saturated with deionized water. After the diffusion period, the plutonium distribution in the bentonite specimen was measured with an alpha scintillation counter, and the iron and sodium distributions were obtained by inductively coupled plasma-mass spectrometry. Plutonium penetrated into the bentonite to a depth of 2 mm, and more than 90% of plutonium remained in corrosion product at the interface. The bentonite around the interface was dark green like green rust or magnetite according to visual observation. Iron was detected throughout the bentonite and there was a particularly high iron concentration from the interface to a depth of 2 mm, whereas the sodium concentration decreased slightly from the interface to 2 mm. We proposed that ferrous ions diffused into bentonite as the iron coupon corroded and precipitated such as magnetite. The magnetite precipitation would decrease the bentonite pH, resulting in the dissolution and migration of plutonium. Small cracks were also observed 2 to 6 mm from the interface and could have been formed by the migration of hydrogen generated by corrosion..
17. tatsumi arima, Kazuya Idemitsu, Yaohiro Inagaki, katsuyuki kawamura, yukio tachi, kenji yotsuji, Diffusion and Adsorption of uranyl ion in Clays: Molecular Dynamics Study, Progress in Nuclear Energy, 92, 286-297, 2016.03.
18. tatsumi arima, Molecular dynamics calculations of heat conduction in actinide oxides under thermal gradient, PROGRESS IN NUCLEAR ENERGY, 10.1016/j.pnucene.2015.06.012, 85, 271-276, 2015.11.
19. tatsumi arima, Oxygen potential measurement of (Pu0.928Am0.072)O2-x at high temperatures, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 10.1080/00223131.2014.986243, 52, 10, 1296-1302, 2015.10.
20. tatsumi arima, Oxygen potential of a prototypic Mo-cermet fuel containing plutonium oxide, JOURNAL OF NUCLEAR MATERIALS, 10.1016/j.jnucmat.2015.06.004, 465, 840-842, 2015.10.
21. tatsumi arima, Thermal conductivity measurement of (Pu1-xAmx)O-2 (x=0.028, 0.072), JOURNAL OF ALLOYS AND COMPOUNDS, 10.1016/j.jallcom.2014.11.205, 629, 92-97, 2015.04.
22. takayuki kasano, tatsumi arima, Kazuya Idemitsu, Yaohiro Inagaki, Crystallographic comparison of zirconium and molybdenum dioxide-based pyrochlores, Progress in Nuclear Energy, 72, 134-139, 2014.04.
23. tatsumi arima, keita yoshida, taku matsumoto, Yaohiro Inagaki, Kazuya Idemitsu, Thermal conductivities of ThO2, NpO2 and their related oxides: Molecular dynamics study, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.11.006, 445, 1-3, 175-180, 2014.02.
24. teppei yamana, tatsumi arima, Yaohiro Inagaki, Kazuya Idemitsu, takatoshi yoshihara, Oxygen diffusion in niobia-doped zirconia as surrogate for oxide film on Zr-Nb alloy: AC impedance analysis, Journal of Nuclear Materials, 10.1016/j.jnucmat.2013.10.015, 443, 1-3, 608-603, 2013.11.
25. taku matsumoto, tatsumi arima, Yaohiro Inagaki, Kazuya Idemitsu, masato kato, teppei uchida, Investigation of O/M Ratio Effect on Thermal conductivity of Oxide Nuclear Fuels by Non-equilibrium Molecular Dynanics Calculation, Journal of Nuclear Materials, 440, 580-585, 2013.09.
26. takahiro ito, tatsumi arima, masashi himi, hiroaki yugo, Atomistic Simulation on the Interfacial Interaction of Metallic Fuel and Structural Materials in SFRs - Molecular Dynamics Model for Pu-Fe system -, Journal of Nuclear Science and Technology, 50, 265-276, 2013.03.
27. K. Yoshida, T. Arima, Y. Inagaki, K. Idemitsu, Masahiko Osaka, Shuhei Miwa , Oxygen potential of hypo-stoichiometric La-doped UO2, Journal of Nuclear Materials, 418, 22-26, 2011.11.
28. M. Nishina, K. Yoshida, T. Arima, Y. Inagaki, K. Idemitsu, I. Sato, Molecular dynamics study on grain boundary diffusion of actinides and oxygen in oxide fuels, Progress in Nuclear Science and Technology, 2, 95-100, 2011.10.
29. T. Nozaki, T. Arima, K. Idemitsu, Y. Inagaki , Synthesis of zirconia sphere particles based on gelation of sodium alginate, Journal of Nuclear Materials, 412, 184-189, 2011.05.
30. I. Sato, K. Tanaka, T. Arima, Diffusion behaviors of plutonium and americium in polycrystalline urania, IOP Conf. Series: Materials Science and Engineering, 9, 12005, 2010.05.
31. T. Arima, K. Yoshida, K. Idemitsu, Y. Inagaki, I. Sato, Molecular dynamics analysis of diffusion of uranium and oxygen ions in uranium dioxide, IOP Conf. Series: Materials Science and Engineering, 9, 12003, 2010.05.
32. T. Uchida, T. Arima, K. Idemitsu, Y. Inagaki , Thermal conductivity of non-stoichiometric americium oxide: A molecular dynamics study, Journal of Nuclear Materials, 400, 3-7, 2010.04.
33. M. Himi, Y. Yamamoto, Y. Nagamine, N. Shirakawa, Y. Uehara, T. Arima, Next Generation Safety Analysis Methods for SFRs-(8) Analysis of Eutectics between Fuel and Steel in Metal Fuel wtith FPMD Code VASP, Proceedings of ICONE17: 17th International Conference on Nuclear Engineering (ICONE17), 2009.06.
34. T. Ito, T. Arima, M. Himi, Next Generation Safety Analysis Methods for SFRs-(7) Potential Model for Classical Molecular Dynamics on Pu-Fe System, Proceedings of ICONE17: 17th International Conference on Nuclear Engineering (ICONE17), 2009.06.
35. T. Arima, K. Idemitsu, Y. Inagaki, Y. Tsujita, M. Kinoshita, E. Yakub, Evaluation of melting point of UO2 by molecular dynamics simulation, Journal of Nuclear Materials, 389 (2009) 149-154, 2009.05.
36. T. Uchida, T. Arima, K. Idemitsu, Y. Inagaki, Thermal conductivities of americium dioxide and sesquioxide by molecular dynamics simulations, Computational Materials Science, 45 (2009) 229-234, 2009.04.
37. T. Arima, K. Miyata, K. Idemitsu, Y. Inagaki , Oxidation properties of Zr-Nb alloys at 973-1273 K in air
, Progress in Nuclear Energy, 51 (2009) 307-312, 2009.03.
38. Y. Tsujita, T. Arima, K. Idemitsu, Y. Suzuki, H. Kumura , Building an Apprication -specific Grid Computing Environment Using ITBL for Nuclear Material Engineering
, Proceedings of ICONE16: 16th International Conference on Nuclear Engineering, 2008.05.
39. M. Himi, H. Kozaki, Y. Yamamoto, S. Hosoda, N. Shirakawa, T. Arima, R & D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology (6) Study of Eutectic Reaction between Materials: FPMD Approach, Proceedings of ICONE16: 16th International Conference on Nuclear Engineering, 2008.05.
40. T. Arima, S. Yamasaki, K. Idemitsu, Y. Inagaki , Equilibrium and Nonequilibrium Molecular Dynamics Simulations of Heat Conduction in Uranium Oxide and Mixed Uranium–plutonium Oxide, Journal of Nuclear Materials, 376 (2008) 139-145, 2008.05.
41. T. Arima, K. Miyata, K. Idemitsu, Y. Inagaki , Oxidation Behavior of Zr-Nb alloys at 973-1273 K in Air
, in Materials Innovations for Next-Generation Nuclear Energy, edited by R. Devanathan, R.W. Grimes, K. Yasuda, B.P. Uberuaga, and C. Meis (Mater. Res. Soc. Symp. Proc. Volume 1043E, Warrendale, PA, 2008), in Materials Innovations for Next-Generation Nuclear Energy, edited by R. Devanathan, R.W. Grimes, K. Yasuda, B.P. Uberuaga, and C. Meis (Mater. Res. Soc. Symp. Proc. Volume 1043E, Warrendale, PA, 2008), 1043-T09-01., 2007.11.
42. T. Matsuo, K. Shimamura, T. Arima, K. Miyata, K. Idemitsu, Y. Inagaki , Evaluation of Mechanical Properties of Stabilized Zirconia and Zirconate Pyrochlore
, in Materials Innovations for Next-Generation Nuclear Energy, edited by R. Devanathan, R.W. Grimes, K. Yasuda, B.P. Uberuaga, and C. Meis (Mater. Res. Soc. Symp. Proc. Volume 1043E, Warrendale, PA, 2008), in Materials Innovations for Next-Generation Nuclear Energy, edited by R. Devanathan, R.W. Grimes, K. Yasuda, B.P. Uberuaga, and C. Meis (Mater. Res. Soc. Symp. Proc. Volume 1043E, Warrendale, PA, 2008), 1043-T09-07., 2007.11.
43. S. Yamasaki, T. Arima, K. Idemitsu, Y. Inagaki, Evaluation of Thermal Conductivity of Hyperstoichiometric UO2+x by Molecular Dynamics Simulation, International Journal of Thermophysics, International Journal of Thermophysics 28 (2007) 661-673., 2007.10.
44. K. Shimamura, T. Arima, K. Idemitsu, Y. Inagaki, Thermophysical Properties of Rare-earth-stabilized Zirconia and Zirconate Pyrochlores as Surrogates for Actinide-doped Zirconia, International Journal of Thermophysics, International Journal of Thermophysics 28 (2007) 1074-1084., 2007.10.
45. T. Arima, E. Ohga, T. Shiragaki, K. Idemitsu, Y. Inagaki , Application of Sol-gel Processing to Synthesis of Ni-YSZ Cermet Membrane, Memoirs of the Faculty of Engineering Kyushu university, Memoirs of the Faculty of Engineering Kyushu university 67 (2007) 95-103., 2007.10.
46. E. Ohga, T. Arima, K. Idemitsu, Y. Inagaki, Sol-gel Preparation and Characterization of Ni-YSZ Cermet Electrode, Progress in Nuclear Energy, Progress in Nuclear Energy 49 (2007) 546-554, 2007.10.
47. T. Uchida, K. Kawashima, T. Arima, K. Idemitsu, Y. Inagaki , Thermophysical Properties of Americium Dioxide by Molecular Dynamics Simulation
, Proceedings of the Asian Thermophysical Properties Conference, Proceedings of the Asian Thermophysical Properties Conference, Paper No. 093., 2007.08.
48. T. Arima, S. Yamasaki, K. Yamahira, K. Idemitsu, Y. Inagaki and C. Degueldre, Evaluation of thermal conductivity of zirconia-based inert matrix fuel by molecular dynamics simulation, Journal of Nuclear Materials, Vol. 352, pp. 309-317, 2006.06.
49. T. Arima, S. Yamasaki, Y. Inagaki, K. Idemitsu, Evaluation of thermal conductivity of hypostoichiometric (U,Pu)O2-x solid solution by molecular dynamics simulation at temperatures up to 2000 K, Journal of Alloys and Compounds, Vol. 415, pp. 43-50, 2006.05.
50. Crystallographic study of zirconate pyrochlore-based inert matrix fuel.
51. T. Arima, K. Idemitsu, K. Yamahira, S. Torikai, Y. Inagaki, Application of internal gelation to sol-gel synthesis of ceria-doped zirconia microspheres as nuclear fuel analogous materials, Journal of Alloys and Compounds, 10.1016/j.jallcom.2004.10.040, 394, 1-2, 271-276, Vol. 394, pp. 271-276, 2005.01.
52. T. Arima, S. Yamasaki, S. Torikai, K. Idemitsu, Y. Inagaki and C. Degueldre, Molecular dynamics simulation of zirconia-based inert matrix fuel, Journal of Alloys and Compounds, 10.1016/j.jallcom.2005.02.041, 398, 1-2, 296-303, Vol. 398, pp. 296-303, 2005.01.
53. T. Arima, S. Yamasaki, Y. Inagaki, K. Idemitsu, Evaluation of thermal properties of UO2 and PuO2 by equilibrium molecular dynamics simulations from 300 to 2000 K, Journal of Alloys and Compounds, 10.1016/j.jallcom.2005.04.003, 400, 1-2, 43-50, Vol. 400, pp. 43-50, 2005.01.
54. T. Arima, K. Fukuyo, K. Idemitsu, Y. Inagaki, Molecular dynamics simulation of yttria-stabilized zirconia between 300 K and 2000 K, Journal of Molecular Liquids, 10.1016/j.molliq.2004.02.038, 113, 1-3, 67-73, Vol. 113, pp. 67-73, 2004.01.
55. T. Arima, M. Takaki, I. Sato, K. Idemitsu, Y. Inagaki, H. Furuya, Reaction of modified SUS316 with tellurium under low oxygen potentials, Corrosion Science, 10.1016/s0010-938X(03)00022-2, 45, 8, 1757-1766, Vol. 45, pp. 1757-1766, 2003.01.
56. T. Arima, T. Tateyama, K. Idemitsu, Y. Ingagaki, Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature: a compatibility study for cermet fuels, Journal of Nuclear Materials, 10.1016/S0022-3115(03)00129-6, 319, 24-30, Vol. 319, pp. 24-30, 2003.01.
57. C. Degueldre, T. Arima, Y.W. Lee, Thermal conductivity of zirconia based inert matrix fuel: Use and abuse of the formal models for testing new experimental data, Journal of Nuclear Materials, 10.1016/S0022-3115(03)00127-2, 319, 6-14, Vol. 319, pp. 6-14, 2003.01.
58. K. Idemitsu, T. Arima, Y. Ingagaki, S. Torikai, Manufacturing of zirconia microsphere doped with erbia, yttria and ceria by internal gelation process as a part of a cermet fuel, Journal of Nuclear Materials, 10.1016/S0022-3115(03)00130-2, 319, 31-36, Vol. 319, pp. 31-36, 2003.01.
59. T. Arima, K. Miyata, Y. Inagaki, K. Idemitsu, Oxidation properties of Zr-Nb alloys at 500-600℃ under low oxygen potentials, Corrosion Science, Vol. 47, pp. 233-446, 1998.01.


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