九州大学 研究者情報
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出光 一哉(いでみつ かずや) データ更新日:2022.05.19

教授 /  工学研究院 エネルギー量子工学部門 エネルギー物質科学


主な研究テーマ
鉄共存系ベントナイト中のセレンの移行挙動
キーワード:亜セレン酸、XAFS、電解移動,ベントナイト,移行挙動、還元環境、鉄腐食
2012.04~2014.03.
セメント系ヨウ素固化体の評価に関する研究
キーワード:ヨウ素、セメント、XAFS、電解移動,ベントナイト,移行挙動、還元環境、鉄腐食
2008.04~2012.03.
電解移動法によるベントナイト中の核種の移行挙動に関する研究
キーワード:電解移動,ベントナイト,移行挙動、還元環境、鉄腐食
2002.04~2010.03.
還元環境でのベントナイト中の核種の拡散挙動に関する研究
キーワード:還元環境,鉄腐食,ベントナイト,拡散
2000.04.
従事しているプロジェクト研究
燃料デブリ分析のための超微量分析技術の開発
2019.09~2024.03, 代表者:永井 康介, 東北大学, 東北大学(日本)
福島第一原子力発電所の廃炉に関して、事故で発生した核燃料デブリの分析手法の確認を行うため、模擬デブリの製造とその物性分析およびその処理・処分に係る迅速な分析工程の確立を目指す。.
ジオミメティクスを活用した放射性核種の長期安定化への技術革新
2019.10~2021.03, 代表者:笹木 圭子, 九大, 九大
放射性廃棄物処分において、処理処分の難しい超半減期かつ陰イオン錯体を形成するヨウ素とセレンの固化法を模索する技術開発を行う。.
電位勾配下でのベントナイト中のイオンの移行挙動に関する研究
1997.10~2009.12, 代表者:出光一哉, 九大, 九大
放射性廃棄物処分場に用いられる人工バリア(ベントナイト)中のイオンの移行挙動を電気化学的方法を用いて解明する。鉄片の電気的腐食によりベントナイト中に還元環境を作り出し、その場での種々のイオンの移動速度の測定を行なう。.
人工バリア相互影響確証試験
1997.10~2007.05, 代表者:宮本真哉, 東芝, 東芝
放射性廃棄物処分場に用いられる人工バリア同士の共存性についての研究を行なう。主にベントナイトの変質およびセメントの変質挙動解明。.
Inert Matrix Fuel Project
1997.10~2004.09, 代表者:C. Degueldre, Paul Scherrer Institute, Switzerland
プルトニウムを軽水炉において燃料として用いる(プルサーマル)が計画されている。しかし、プルトニウムをウランと共に燃料として用いた場合、実質プルトニウムの消費にはならない。このためウランを含まない燃料の研究が行われている。その第一候補母材はジルコニウム酸化物であり、優れた化学的安定性、耐放射線損傷性、プルトニウムの固溶安定性を持つ。しかし、熱伝導率が低いという欠点がある。そこで、種々の複合材料を用いた燃料研究が行われている。.
研究業績
主要著書
主要原著論文
1. Kazuya Idemitsu, Hajime Arimitsu, Masayuki Hirakawa, Keisuke Yoshida, Yaohiro Inagaki, Tatsumi Arima, Effect of carbonate on the migration behavior of neptunium in compacted bentonite, MRS Advances 2022 ,online , 31th January 2022, Springer, DOI: 10.1557/s43580-022-00210-9, 7, 7-8, 140-143, 2022.01.
2. Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Keisuke Yoshida, Speciation by XANES of copper migrated into compacted bentonite using electromigration techniques, MRS Advances Vol.6 Issue 4 , pp. 80-83 , Jamuary 2021, Cambridge University Press, DOI: 10.1557/s43580-021-00026-z, 5, 3-4, 141-147, 2021.04.
3. Kazuya Idemitsu, Ryota Yamada, #Masayuki Hirakawa, #Yuki Kakoi, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Copper in Compacted bentonite Using Electromigration Technique, MRS Advances Vol.5 Issue3-4, pp. 141-147, Jamuary 2020, Cambridge University Press, DOI: 10.1557/adv.2020.55, 5, 3-4, 141-147, 2020.01.
4. Kazuya Idemitsu, Ryota Yamada, Masayuki Hirakawa, Yuki Kakoi, Hajime Arimitsu, Yaohiro Inagaki, Tatsumi Arima, Effect of Carbonate on the Migration Behavior of Strontium in Compacted Bentonite, MRS Advances, 10.1557/adv.2019.81, 4, 17-18, 1021-1027, 2019.01, [URL], The apparent diffusion coefficients of strontium in compacted bentonites were investigated at various concentrations of NaHCO3. Purified sodium bentonite Kunipia-F® was compacted with a jig into cylindrical pellets 10 mm in diameter and 10 mm high with dry densities of 1.0 to 1.6 Mg/m 3 . Each bentonite pellet was inserted into an acrylic resin column and saturated with carbonated water containing 0.1 to 1.0 M NaHCO3 for more than 1 month. The face of the bentonite specimen was spiked with 5 μL of 1.0 M SrCl2 tracer solution. After a few weeks, the strontium diffusion profiles were measured by inductively coupled plasma-mass spectrometry. The apparent diffusion coefficients of strontium decreased slightly with increasing dry density. NaHCO3 concentrations of 0.5 M decreased the apparent diffusion coefficients of strontium by half at a dry density of 1.0 Mg/m 3 and quarter at 1.6 Mg/m 3 . At a higher NaHCO3 concentration of 1.0 M, no strontium diffusion profile was observed, whereas white precipitate was observed on the face of the bentonite specimen where it was spiked with strontium. This white precipitate could be strontianite, which is strontium carbonate. Diffusion experiments using cesium were carried out for comparison, and the presence of carbonate had no effect on the apparent diffusion coefficient..
5. Kazuya Idemitsu, Kazuyuki Fujii, Noriyuki Maeda, Yuki Kakoi, Noriya Okubo, Yaohiro Inagaki, Tatsumi Arima, Effect of Carbonate on the Migration Behavior of Lanthanides in Compacted Bentonite, MRS Advances, 10.1557/adv.2018.184, 3, 21, 1155-1160, 2018.01, [URL], The apparent diffusion coefficients of La, Nd, Eu, Dy, Er, and Lu in compacted bentonites were investigated at various bicarbonate concentrations. The apparent diffusion coefficients of these lanthanides tended to decrease with increasing dry density. At bicarbonate concentrations below 0.25 M, lanthanum had the largest diffusion coefficient (ca. 10-13 m2/s) at 1.0 Mg/m3, and the diffusion coefficient decreased with increasing atomic number. On the other hand, at bicarbonate concentrations above 0.25 M, lutetium had the largest diffusion coefficient, and the diffusion coefficient decreased with decreasing atomic number. In particular, lanthanum and neodymium had diffusion coefficients below 10-14 m2/s, even at 1.0 Mg/m3. The diffusion coefficient of europium was around 10-13 m2/s at 1.0 Mg/m3 and was influenced less by the bicarbonate concentration. The diffusion coefficient of lutetium increased from 2 × 10-14 to 10-12 m2/s as the bicarbonate concentration was increased to 1.0 M. The concentration of carbonate ion in the pore water of bentonite is estimated to be much lower than that in solutions in contact with bentonite from the viewpoints of solubility and chemical species of lanthanides..
6. 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, [URL], 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..
7. Ryo Hamada, Noriyuki Maeda, Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Daisuke Akiyama, Kenji Konashi, Makoto Watanabe, Shin Ichi Koyama, Effect of pH on Plutonium Migration Behavior in Compacted Bentonite, MRS Advances, 10.1557/adv.2017.183, 1, 61, 4011-4017, 2016.01, [URL], In disposing of high-level radioactive waste, the drop in pH in the repository as the iron overpack corrodes must be considered. Plutonium migration behavior may be affected by the pH of pore water in compacted bentonite barriers in high-level waste repositories. To examine the effect of pH on migration behavior, H-bentonite was prepared by treating Japanese Na-bentonite, Kunipia-F, with hydrochloric acid. Diffusion experiments were performed with mixtures of Na- and H-bentonites. The pH value in the pore water of the water-saturated bentonite mixtures decreased from 8 to 3 as the mixing ratio of H-bentonite increased. Diffusion experiments were carried out by using 238Pu then apparent diffusion coefficients were determined from the plutonium distribution in the specimens. The apparent diffusion coefficients were on the order of 10-13 to 10-12 m2/s at pH values lower than 4, whereas they were less than 10-14 m2/s at pH values higher than 6.5. These results indicate that plutonium diffused faster as Pu3+ or PuO2 2+ due to disproportionation at lower pH while plutonium could be retarded as Pu(OH)4 0 by sorption on bentonite at higher pH..
8. Kazuya Idemitsu, Tomofumi Sakuragi, Current Status of Immobilization Techniques for Geological Disposal of Radioactive Iodine in Japan, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXVIII, 10.1557/opl.2015.297, Vol.1744, pp., 2015.04.
9. Daisuke Akiyama, Kazuya Idemitsu, Yaohiro Inagaki, tatsumi arima, Kenji Konashi, Shinichi Koyama, Migration behavior of plutonium affected by ferrous ion in compacted bentonite by using electrochemical technique, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXVII, Vol.1665, pp.79-84, 2015.02.
10. Kazuya Idemitsu, Hikaru Kozaki, Daisuke Akiyama, Masanao Kishimoto, Masaru Yuhara, Noriyuki Maeda, Yaohiro Inagaki, Tatsumi Arima, Migration behavior of selenium in the presence of iron in Bentonite, Journal of Fluid Mechanics, 10.1557/opl.2014.641, 1665, 2014.11, [URL], Selenium (Se) is an important element for assessing the safety of high-level waste disposal. Se is redox-sensitive, and its oxidation state varies from -2 to 6 depending on the redox conditions and pH of the solution. Large quantities of ferrous ions formed in bentonite due to corrosion of carbon steel overpack after the closure of a repository are expected to maintain a reducing environment near the repository. Therefore, the migration behavior of Se in the presence of Fe in bentonite was investigated by electrochemical experiments. Na2SeO3 solution was used as tracer solution. Dry density range of bentonite was from 0.8 to 1.4 ×103 kg/m3. Results indicated that Se was strongly retained by the processes such as precipitation reaction with ferrous ions in bentonite. Se K-edge X-ray absorption near-edge structure (XANES) measurements were performed at the BL-11 beamline at SAGA Light Source, and the results revealed that the oxidation state of Se in the bentonite remained Se(IV)..
11. Kazuya Idemitsu, Yoshihiko Matsuki, Masanao Kishimoto, Yaohiro Inagaki, Tatsumi Arima, Yoshiko Haruguchi, Yu Yamashita, Michitaka Sasoh, Migration of Iodine Solidified in Ettringite into Compacted Bentonite, Advances in Materials Science for Environmental and Energy Technologies II, 10.1002/9781118751176, 241, 23-34, 2013.08, Nuclear reprocessing plants produce materials containing radioactive iodine-129. Cement can be used to immobilize and solidify radioactive iodine by fixing it in the form of the iodate ion in the mineral ettringite. Because the half-life of 129I is 15.7 million years, radioactive wastes that contain 129I require disposal by burial deep underground. In the disposal of such wastes, compacted bentonite is used as a buffer material as well as the disposal of high-level radioactive wastes. Because there is a concern that radioactive iodine could leak from disposed wastes by diffusion through compacted bentonite over a long period, the release behavior of iodine from ettringite was examined by means of electromigration studies in compacted bentonite. Most of the calcium and iodine is retained within the structure of iodate-containing ettringite (IO3-AFt), even if the chemical form of iodine changes from iodate to iodide ion as a result of reaction with ferrous ions. However, acid produced by precipitation of ferric hydroxide might destroy the structure of IO3-AFt in cementitious materials and cause release of iodine. It might therefore be necessary to adopt measures to prevent intrusion of acid or ferrous ions into cementitious wastes containing radioactive iodine..
12. Kazuya Idemitsu, Daisuke Akiyama, Yoshihiko Matsuki, Yusuke Irie, Yaohiro Inagaki, Tatsumi Arima, Migration Behaviour of Lanthanides in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method
, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXV, Vol.1475, pp.611-616, 2012.07.
13. Y.Matsuki, K.Idemitsu, D.Akiyama, Y.Inagaki, T.Arima, Migration Behavior of Iodine in Compacted Bentonite, Proceedings of the10th International Conference GLOBAL2011, No.500826, 2011.12.
14. Kazuya Idemitsu, Daisuke Akiyama, Akira Eto, Yoshihiko Matsuki, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Alkali Earth Ions in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXIV, Vol.1265, pp.227-232, 2010.11.
15. Kazuya Idemitsu, Hirotomo Ikeuchi, Daisuke Akiyama, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Potassium and Rubidium in Compacted Bentonite Under Reducing Condition with Iron Corrosion Product, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXIII, Vol.1193 pp.453-460, 2010.02.
16. K. Idemitsu, H. Ikeuchi, S. A. Nessa, Y. Inagaki, T. Arima, S. Yamazaki, T. Mitsugashira, M. Hara, Y. Suzuki, Migration Behavior of Plutonium in Compacted Bentonite Under Reducing Conditions Controlled with Potentiostat, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXII, Vol.1124 pp.283-288, 2009.06.
17. Kauzya. IDEMITSU, Syeda Afsarun NESSA, Shigeru. YAMAZAKI, Hirotomo IKEUCHI, Yaohiro. INAGAKI , T. ARIMA, Migration Behavior of Ferrous Ion in Compacted Bentonite Under Reducing Conditions Controlled with Potentioatat., Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXXI, Vol.1107, pp.501-508, 2008.09.
18. K. IDEMITSU, Y. YAMASAKI, Syeda Afsarun NESSA, Y. INAGAKI , T. ARIMA, T.MITSUGASHIRA, M.HARA and Y.SUZUKI, Migration Behavior of Plutonium in Compacted Bentonite Under Reducing Condition using Electromigration, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXX, Vol.985, pp.443-448, 2007.06.
19. Syeda Afsarun NESSA, K. IDEMITSU, Y. YAMASAKI, Y. INAGAKI and T. ARIMA, Measurement of pH of the Compacted Bentonite under the Reducing Condition, Memoirs of the Faculty of Engineering Kyushu University, Vol. 67 No.1 pp. 25-31, 2007.03.
20. S. MIYAMOTO, S. UEHARA, M. SASOH, M. SATO, M. TOYOHARA, K.IDEMITSU, S. MATSUMURA, Characterization of Cement Alteration Process by Transmission Electron Microscopy with High Spatial Resolution, Journal of Nuclear Science and Technology, Vol.43, No.11, pp.1370-1378, 2006.11.
21. 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., Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXIX, Vol.932, pp.321-328, 2006.06.
22. K. Yamaguchi, Y. Inagaki, T. Saruwatari, K. Idemitsu, T. Arima, H. Yoshikawa, M. Yui, Kinetics of Aqueous Alteration of P0798 Simulated Waste Glass in the Presence of Bentonite., Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXIX, Vol.932, pp.385-392, 2006.06.
23. K. Idemitsu, M. Yamamoto, Y. Yamasaki, Y. Inagaki , T. Arima, Migration Behavior of Cesium in Compacted Bentonite under Reducing Conditions Using Electromigration., Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXIX, Vol.932, pp.943-950, 2006.06.
24. Tatsumi ARIMA, Sho YAMASAKI, Yaohiro INAGAKI, Kazuya 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.
25. Y. INAGAKI, A. SHINKAI, K. IDEMITSU, T. ARIMA, H. YOSHIKAWA, M. YUI, Aqueous alteration of Japanese simulated waste glass P0798: Effects of alteration-pjase formation on alteration rate and cesium retention, Journal of Nuclear Materials, 354 (2006) 171-184, 2006.04.
26. M. OBATA, Y. INAGAKI, T. SASAKI, K.IDEMITSU, Aqueous Corrosion Behavior of Glass Phase of Simulated Low Level Waste Form Produced by In-can type Induction-Heated Melting, Journal of Nuclear Science and Technology, Vol.43, No.2, pp.270-275, 2006.02.
27. X.XIA, K. IDEMITSU, T. ARIMA, Y. INAGAKI, T. ISHIDERA, S. KUROSAWA, K. IIJIMA, H. SATO, Corrosion of carbon steel in compacted bentonite and its effect on neptunium diffusion under reducing condition, Applied Clay Science, 10.1016/j.clay.2004.01.002, 28, 1-4, 89-100, Vol.28, pp.89-100, 2005.01.
28. K. IDEMITSU, X. XIA, Y. KIKUCHI, Y. INAGAKI, T. ARIMA, Migration Behavior of Ferrous Ions in Compacted Bentonite under Reducing Condition by Using Electromigration, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXVIII, 824, 491-496, Vol.824, pp.491-496, 2004.12.
29. K. IDEMITSU, X. XIA, Y. KIKUCHI, Y. INAGAKI, T. ARIMA, T.MITSUGASHIRA, M.HARA,Y.SUZUKI, Migration Behavior of Plutonium in Compacted Bentonite under Reducing Condition by Using Electromigration, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXVII, 807, 591-596, Vol.807, pp.591-596, 2004.04.
30. K.IDEMITSU, S.YANO, X.XIA, Y.KIKUCHI, Y.INAGAKI, T.ARIMA, Migration behavior of iron ion in compacted bentonite under reducing condition by using electromigration, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXVI, 757, 657-664, Vol.757, pp.657-664, 2004.03.
31. T. Arima, T. Tateyama, K. Idemitsu, Y. Inagaki, 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 24-30, 2003.07.
32. K. Idemitsu, T. Arima, Y. Inagaki, S. Torikai, M.A. Pouchon, 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 31-36, 2003.07.
33. 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 1757-1766, 2003.03.
34. X.XIA, K.IDEMITSU, T.MITSUGASHIRA, T.ARIMA, Y.INAGAKI, Plutonium Determination in Compacted Bentonite by Using PERALS, Journal of Nuclear Science and Technology, Suppllement 3, pp.572-575, 2002.11.
35. Y.INAGAKI, K.IDEMITSU, T.ARIMA, Alteration-phase Formation and Associated Cesium Release during Alteration of R7T7 Waste Glass, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXV, Vol.713, pp.589-596, 2002.06.
36. X.XIA, Y.INAGAKI, K.IDEMITSU, T.ARIMA, Iodine Release from Silver Iodide under Reducing Condition with Iron-bearing Materials, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXV, 713, 783-790, Vol.713, pp.783-790, 2002.06.
37. N.SAKAMOTO, T.ISHIDA, T.ARIMA, K.IDEMITSU, Y.INAGAKI, Concentrations of Radiocarbon and Isotope Compositions of Stable Carbon in Food, Journal of Nuclear Science and Technology, 10.3327/jnst.39.323, 39, 4, 323-328, Vol.39, No.4, pp.323-328, 2002.04.
38. I. Sato, M. Takaki, T. Arima, H. Furuya, K. Idemitsu, Y. Inagaki, Oxidation behavior of modified SUS316 (PNC316) stainless steel under low oxygen partial pressure, Journal of Nuclear Materials, 10.1016/S0022-3115(02)00872-3, 304, 1, 21-28, Vol.304 pp.21-28, 2002.04.
39. T.ARIMA, T.MASUZUMI, H. FURUYA, K.IDEMITSU, Y.INAGAKI, Reaction of Zircaloy-4 with tellurium under different oxygen potentials, Journal of Nuclear Materials, 10.1016/S0022-3115(02)00711-0, 301, 2-3, 90-97, Vol.301, pp.90-97, 2002.01.
40. T.ARIMA, T.MASUZUMI, H. FURUYA, K.IDEMITSU, Y.INAGAKI, The oxidation kinetics and the structure of the oxide film on Zircaloy before and after the kinetic transition, Journal of Nuclear Materials, 10.1016/S0022-3115(01)00453-6, 294, 1-2, 148-153, Vol.294, pp.148-153, 2001.06.
41. K.IDEMITSU, X.XIA, T.ICHISHIMA, H.FURUYA, Y.INAGAKI, T.ARIMA, T.MITSUGASHIRA, Y.SUZUKI, Diffusion of Pu in Compacted Bentonites in the Reducing Condition with Corrosion Products of Iron, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXIII, Vol.608, pp.261-266, 2000.11.
42. M. BURGHARTZ, G. LEDERGERBER, F. INGOLD, T. XIE, F. BOTTA, K.IDEMITSU, Concepts and First Fabrication Studies of Inert Matrix Fuel for the Incineration of Plutonium, Proceedings of Workshop on Advanced Reactors with Innovative Fuels, pp.267-276, 1999.11.
43. A.OKAMOTO, K.IDEMITSU, H.FURUYA, Y.INAGAKI, T.ARIMA, Distribution Coefficients and Apparent Diffusion Coefficients of Cs in Compacted Bentonites, Proceedings of Materials Research Society Symposium on Scientific Basis for Nuclear Waste Management XXII, 556, 1091-1098, Vol.556, pp.1091-1098, 1999.11.
44. I.SATO, H. FURUYA, T.ARIMA, K.IDEMITSU, K.YAMAMOTO, Behavior of Metallic Fission Products Zirconium and Barium in Fasr Reactor Fuel Irradiated to High Burnup, Journal of Nuclear Science and Technology, Vol.36, No.9, pp.775-780, 1999.09.
45. I.SATO, H. FURUYA, T.ARIMA, K.IDEMITSU, K.YAMAMOTO, Behavior of Metallic Fission Products in Uranium-plutonium Mixed Oxide Fuel, Journal of Nuclear Materials, 10.1016/S0022-3115(99)00071-9, 273, 3, 239-247, Vol.273, pp.239-247, 1999.02.
46. T.ARIMA, K.MORIYAMA, N.GAJA, H.FURUYA, K.IDEMITSU, Y.INAGAKI, Oxidation kinetics of Zircaloy-2 between 450°C and 600°C in Oxidizing Atmosphere, Journal of Nuclear Materials, 10.1016/S0022-3115(98)00069-5, 257, 1, 67-77, Vol.257, pp.67-77, 1998.04.
47. Kazuya Idemitsu, Y. Tachi, H. Furuya, Yaohiro Inagaki, Tatsumi Arima, Diffusion of Cs and Sr in compacted bentonites under reducing conditions and in the presence of corrosion products of iron, Materials Research Society Symposium - Proceedings, 506, 1997.12, In high-level waste repositories, a carbon steel overpack will be corroded by consuming oxygen trapped in the repository after closure. Iron corrosion products are expected to interfere with migration of radionuclides by filling the pore in bentonite and sorbing radionuclides. In this study the apparent diffusion coefficients of cesium and strontium were measured in compacted Na-bentonites (Kunigel V1 and Kunipia F, JAPAN) contacted with carbon steel and its corrosion products under reducing conditions or without carbon steel under oxidizing conditions for comparison. The apparent diffusion coefficients of cesium with and without corrosion product were 2.2 to 13×10-12 m2/s. The apparent diffusion coefficients of strontium with and without corrosion product were 3.1 to 2.5×10-12 m2/s. There were significant effects of dry density (0.8 to 2.0 g/cm3) and montmorillonite contents (50% for Kunigel V1 or 100% for Kunipia F). The presence of corrosion product decreased the apparent diffusion coefficients of Cs in both bentonites and that of Sr in Kunigel V1, especially at low dry density. This may be due to corrosion product filling the pore in the bentonite, decreasing the free pore size and density for diffusion..
48. Kazuya Idemitsu, Hirotaka Furuya, Teruo Hara, Yaohiro Inagaki, Migration of cesium, strontium and cobalt in water-saturated inada granite, journal of nuclear science and technology, 10.1080/18811248.1992.9731551, 29, 5, 454-460, 1992.05, [URL], Diffusivities of Cs, Sr and Co were measured in a water-saturated granite in an attempt to investigate the migration of radionuclides into the matrix of the rock. The measured penetration profiles of every tracer were composed of two parts. There were a steep slope near the surface and a gradual slope in the deeper part. These profiles were successfully explained by considering two diffusion paths in the granite. One diffusion path was fissure with a width of a few microns and another was network of submicron pores. The volume of submicron pores was approximately 80% of the total pore volume in the granite. The orders of magnitude of apparent diffusivities for all nuclides were 10"11 to 10|12m2/s through the fissure and 10_14mz/s through the network of pores. The ratio of geometrical factors in the two paths was also calculated from each apparent diffusivity and was almost unity. This calculated ratio suggests that the pore network in the granite matrix has a similar shape to the fissure, thus the microstructure of the granite seems to be fractal..
49. Kazuya Idemitsu, Katsuhiko Ishiguro, Yasuhisa Yusa, Noriaki Sasaki, Naomi Tsunoda, Plutonium diffusivity in compacted bentonite, Engineering Geology, 10.1016/0013-7952(90)90028-Y, 28, 3-4, 455-462, 1990.01, [URL], Measurements on plutonium diffusivity in water-saturated compacted bentonite were carried out. Representative specimens of sodium bentonite were taken from the Tsukinuno and Kuroishi mines situated in northeast Japan. Tsukinuno bentonite was divided into three types: raw type, purified Na-type, and H-type which was prepared by treating Na-type bentonite with hydrochloric acid. Kuroishi bentonite contained chlorite as impurity. H-type bentonite was used as reference for the convenience of profile measurement in bentonite, since plutonium diffusivity in H-type bentonite was considered to be larger than that in Na-type bentonite because of low pH and low swelling pressure of H-type bentonite. Sampled bentonite was compacted into pellets of 20 mm in diameter and 20 mm in height. Bulk densities of these specimens were 1200-1800 kg/m3 for purified Na-type and H-type bentonite and 1600 kg/m3 for raw type bentonite. Plutonium profiles obtained in H-type bentonite can be explained by diffusion equation with constant concentration source. Diffusivity ranges from 10-13 to 10 12 m2/s for H-type and Kuroishi impure sodium bentonite. Diffusivity in both raw type and purified Tsukinuno bentonite was was estimated to less than 10-14 M2/s. Diffusivity in H-type bentonite showed a tendency to decrease with increasing density. Influence of in bentonite was also studied. Quartz content up to 50% or hematite content up to 1% did not influence diffusivity significantly in H-type bentonite. The chemical species of plutonium in pore water of Na-type and H-type were estimated Pu(OH)3-; and PuO2-, respectively..
50. Masayasu Sugisaki, Satoru Mukai, Kazuya Idemitsu, Hirotaka Furuya, Isotope effect in heat of transport of H, D and T in Nb, Journal of Nuclear Materials, 10.1016/0022-3115(83)90346-X, 115, 1, 91-94, 1983.03, [URL], The thermal diffusion of hydrogen isotopes, H and D, in Nb was studied at an average temperature of 168°C. By analyzing the redistribution of hydrogen in Nb on the basis of the irreversible thermodynamics, the heat of transport Q* was determined for H and D as 9.5 kJ/mol and 16.0 kJ/mol, respectively. The large isotope dependence of Q* was concluded by comparing these values with the value of 18.8 kJ/mol for T, which was previously reported by the present authors. The diffusion coefficients of H and D were also determined from the transient process of redistribution and found to be in good agreement with those based on the Gorsky effect..
51. Masayasu Sugisaki, Kazuya Idemitsu, Satoru Mukai, Hirotaka Furuya, Thermal diffusion of tritium in Nb metal, Journal of Nuclear Materials, 10.1016/0022-3115(82)90811-X, 104, C, 1493-1497, 1981.01, [URL], Thermal diffusion phenomena of tritium in Nb metal are studied for temperatures between 100°-300°C. Some special types of apparatus and samples are developed to determine the distribution of tritium in the transient state of the thermal diffusion. By least squares fitting of the experimental data to the theoretical curve based on irreversible thermodynamics, the heat of transport, Q*, and the diffusion coefficient, D, of tritium at an average temperature of 200°C are determined to be 18.0 kJ/mol and 1.6 x 10-5 cm2/sec, respectively. The importance of the thermal diffusion phenomena is discussed in connection with tritium permeation through the first wall of a nuclear fusion reactor..
主要総説, 論評, 解説, 書評, 報告書等
1. 出光 一哉, ICP-MS/MSを用いたベントナイト中のNpの分析について, 環境管理 第50号, 27-31, 2021.07, ICP-MS/MSによるベントナイト中のNpの分析法について、誤差や妨害の要因や分析精度について解説した。.
2. 出光 一哉, 海洋放出される福島第一原発事故のALPS処理水とは?, 化学 vol.76(7), 12-16, 2021.07, 福島第一原子力発電所の事故によって生じた放射性廃液の処理とその処理水の処分法と安全性について解説した。.
3. 出光 一哉、小崎 完, 廃炉で生じる放射性廃棄物と燃料デブリの処分, 化学 vol.76(3), 35-36, 2021.03, 原子力発電所の事故によって生じる廃棄物の処分に関して、現状と課題、研究開発の例を解説した。.
4. 出光 一哉, 放射性廃棄物固化体の特徴と原子力事故への適用性, セラミックス vol.47, 11, 855-858, 2012.03, 放射性廃棄物固化体の特徴と原子力発電所の事故によって生じる廃棄物の処理への適用性について、国内外の例を示し解説した。.
5. 出光一哉, 放射性廃棄物固化体の特徴と原子力事故への適用性, セラミックスVol.47,No.11,pp.1-4, 2012.11, 福島第一原子力発電所事故の収束に向けた取組みにおいて、2011年12月にステップ2の完了が宣言された。原子炉の冷温停止状態を支える循環注水冷却に関しては、仮設の水処理設備が稼働しているが、恒久的な水処理設備の設置、汚染水処理で発生した2次廃棄物の保管・処理・処分への取り組みも求められている。本稿では、汚染水処理等によって発生した固体廃棄物の減容/固化への適用が期待される固化法について解説した。.
6. 出光一哉 山岸功(日本原子力研究開発機構) 三村均(東北大学), 福島第一原子力発電所高汚染水の処理処分の課題 ー処分を見据えた対応策の提言ー, 日本原子力学会誌「アトモス」Vol.54,No.3,pp.166-170, 2012.03, 福島第一原子力発電所事故の収束に向けた取組みにおいて、2011年12月にステップ2の完了が宣言された。原子炉の冷温停止状態を支える循環注水冷却に関しては、仮設の水処理設備が稼働しているが、恒久的な水処理設備の設置、汚染水処理で発生した2次廃棄物の保管・処理・処分への取り組みも求められている。本稿では、汚染水処理の現状を整理し、吸着剤の性能、今後の処理・処分に関わる技術的課題を解説する。.
7. 出光一哉, 放射性物質を閉じ込める粘土, 環境 九州大学環境安全センター広報 環境報告書2011(抜粋), 2012.03, 放射性廃棄物を安全に処分するシステムとして多重バリアシステムが検討されている。バリア材の一つとしてベントナイト粘土がある。この粘土は水を吸って膨張する性質、水の流れを止める能力、陽イオンをイオン交換し移行を遅延する能力等を持つ。このため、多重バリアシステムにおいてベントナイト粘土を施行することにより、陽イオンの形態をとる放射性物質の移行を遅延することができ、十分な厚さがあれば、ベントナイト内での減衰が期待される。.
主要学会発表等
1. 出光 一哉, [2K_PL03] パネルディスカッション 研究施設等廃棄物の埋設事業へ向けた取り組みについて, 日本原子力学会2022春の年会, 2022.03.
2. Kazuya Idemitsu, Effect of Carbonate on the Migration Behavior of Neptunium in Compacted Bentonite, Scientific Basis for Nuclear Waste Management 2021, 2021.10.
3. 出光 一哉, Diffusion Behavior of Neptunium - Effect of Carbonate -, 2021 大洗研究会, 2021.10.
4. Kazuya Idemitsu, Speciation by XANES of Copper migrated into Compacted Bentonite Using Electromigration Techniques, Scientific Basis for Nuclear Waste Management 2020, 2020.12.
5. Kazuya Idemitsu, Diffusion Behavior of Pu and Np in Bentonite, GIMRT Joint International Symposium on Radiation Effects in Materials and Actinide Science: GIMRT-REMAS2020, 2020.10.
6. Kazuya Idemitsu, #Keisuke Yoshida, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Copper in Compacted Bentonite Using Electromigration Techniques, Scientific Basis for Nuclear Waste Management 2019, 2019.10.
7. Kazuya Idemitsu, #Ryota Yamada, #Masayuki Hirakawa, #Yuki Kakoi, #Hajime Arimitsu, Yaohiro Inagaki, Tatsumi Arima, Effect of Carbonate on the Migration Behavior of Strontium in Compacted Bentonite, Scientific Basis for Nuclear Waste Management 2018, 2018.11.
8. Kazuya Idemitsu, #Yuki Kakoi, #Hajime Arimitsu, Yaohiro Inagaki, Tatsumi Arima, Ultra-trace level measurement of neptunium in bentonite by using ICP-QQQ, International Conference on Ceramic Materials and Components for Energy and Environmental Applications (CMCEE-12), 2018.07.
9. Kazuya Idemitsu, Kazuyuki Fujii, Noriyuki Maeda, Yuki Kakoi, Noriya Okubo, Yaohiro Inagaki, Tatsumi Arima, Effect of Carbonate on the Migration Behavior of Lanthanides in Compacted Bentonite, Scientific Basis for Nuclear Waste Management 2017, 2017.11.
10. 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, Scientific Basis for Nuclear Waste Management XL, 2016.11.
11. Kazuya Idemitsu, Ryo Hamada, Yoshitaka Ogawa, Noriya Okubo, Yaohiro Inagaki, Tatsumi Arima, Salinity Dependence of Apparent Diffusion Coefficients of Selenite, Selenate, Molybdate and Iodate in Compacted Bentonite, Goldschmidt2016, 2016.06.
12. Yaohiro Inagaki, Ryo Matsumoto, Kazuya Idemitsu, Tatsumi Arima, Dissolution Kinetics of a Simplified Nuclear waste Glass, ISG, in MgCl2 Solution, Goldschmidt2016, 2016.06.
13. 出光 一哉, OV0404 福島原発事故で発生した廃棄物の合理的な処理・処分システム構築に向けた基盤研究 (4)廃棄物処分研究の成果 高塩濃度及び従来と異なる廃棄物が処分に与える影響, 日本原子力学会2016春の年会, 2016.03.
14. 小川 由貴, 出光 一哉, 浜田 涼, 大久保 徳弥, 稲垣 八穂広, 有馬 立身, 2F01 福島原発事故で発生した廃棄物の合理的な処理・処分システム構築に向けた基盤研究(55)ベントナイト中のホウ素の拡散に対する塩強度の影響, 日本原子力学会2016春の年会, 2016.03.
15. Ryo Hamada, Noriyuki Maeda, Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Daisuke Akiyama, Kenji Konashi, Makoto Watanabe, Shinichi Koyama, Effect of pH on Plutonium Migration Behavior in Compacted Bentonite, Scientific Basis for Nuclear Waste Management XXXIX, 2015.10.
16. Kazuya Idemitsu, Tomofumi Sakuragi, Immobilization Techniques for Geological Disposal of Radioactive Iodine in Japan, American Ceramics Society MS&T'15, 2015.10.
17. 出光 一哉, 浜田 涼, 小川 由貴, 大久保 徳弥, 稲垣 八穂広, 有馬 立身, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構 築に向けた基盤研究
47)モンモリロナイト含有率の異なるベン トナイト中における陰イオンの拡散挙動のイオン強度依存性, 日本原子力学会「2015秋の大会」, 2015.09.
18. 浜田 涼, 出光 一哉, 前田 範之, 稲垣 八穂広, 有馬 立身, 秋山 大輔, 小無 健司, 渡部 信, 小山 真一, ベントナイト中におけるプルトニウムの移行挙動に与える pH の影響, 日本原子力学会「2015春の年会」, 2015.03.
19. 出光 一哉, 湯原 勝, 小川 由貴, 稲垣 八穂広, 有馬 立身, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構 築に向けた基盤研究
39)ベントナイト中の陰イオンの拡散を支配する有効空隙率のイオン強度依存性, 日本原子力学会「2015春の年会」, 2015.03.
20. 浜田 涼, 出光 一哉, 前田 範之, 稲垣 八穂広, 有馬 立身, 秋山 大輔, 小無 健司, 渡部 信, 小山 真一, ベントナイト中におけるプルトニウムの移行挙動に与える pH の影響, 京都大学「アクチニド元素の化学と工学」専門研究会-アクチニド基礎化学研究の方向性-, 2015.02.
21. Kazuya Idemitsu, Tomofumi Sakuragi, Current Status of Immobilization Techniques for Geological Disposal of Radioactive Iodine in Japan, Scientific Basis for Nuclear Waste Management XXXVIII, 2014.12.
22. 出光 一哉, 湯原 勝, 浜田 涼, 小崎 晃, 岸本 将尚, 稲垣 八穂広, 有馬 立身, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構 築に向けた基盤研究
(28)圧密ベントナイト中のオキシ陰イオンの拡散挙動, 日本原子力学会「2014秋の大会」, 2014.09.
23. Noriyuki Maeda, Kazuya Idemitsu, Yusuke Irie, Daisuke Akiyama, Hikaru Kozaki, Tatsumi Arima, Yaohiro Inagaki, Migration Behavior of Cesium Molybdate in Compacted Bentonite, Scientific Basis for Nuclear Fuel Cycle II, 2014.08.
24. Kazuya Idemitsu, Hikaru Kozaki, Masaru Yuhara, Tatsumi Arima, Yaohiro Inagaki, Migration Behavior of Selenite in Compacted Bentonite, Scientific Basis for Nuclear Fuel Cycle II, 2014.08.
25. Tatsumi Arima, Kazuya Idemitsu, Yaohiro Inagaki, Katsuyuki Kawamjra, Yukio Tachi, Kenji Yotsuji, Diffusion and Adsorption of Uranyl ion in Clays: Molecular Dynamics Study, Scientific Basis for Nuclear Fuel Cycle II, 2014.08.
26. 出光 一哉, 小崎 晃, 湯原 勝, 稲垣 八穂広, 有馬 立身, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構 築に向けた基盤研究;(18)ベントナイト中の亜セレン酸の拡散の 活性化エネルギーの塩強度依存性, 日本原子力学会「2014春の年会」, 2014.03.
27. 出光 一哉, 小崎 晃, 湯原 勝, 稲垣 八穂広, 有馬 立身, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構 築に向けた基盤研究;(18)ベントナイト中の亜セレン酸の拡散の 活性化エネルギーの塩強度依存性, 日本原子力学会「2014春の年会」, 2014.03.
28. Daisuke Akiyama, Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Kenji Konashi, Shinichi Koyama, Migration behavior of plutonium affected by ferrous ion in compacted bentonite by using electrochemical technique, Scientific Basis for Nuclear Waste Management XXXV, 2013.10.
29. Kazuya Idemitsu, Hikaru Kozaki, Daisuke Akiyama, Masanao Kishimoto, Masaru Yuhara, Noriyuki Maeda, Yaohiro Inagaki, tatsumi arima, Migration Behavior of Selenium in the Presence of Iron in Bentonite, Scientific Basis for Nuclear Waste Management XXXV, 2013.10, Selenium (Se) is an important element for assessing the safety of high-level waste disposal. Se is redox-sensitive, and its oxidation state varies from -2 to 6 depending on the redox conditions and pH of the solution. Large quantities of ferrous ions formed in bentonite due to corrosion of carbon steel overpack after the closure of a repository are expected to maintain a reducing environment near the repository. Therefore, the migration behavior of Se in the presence of Fe in bentonite was investigated by electrochemical experiments. Na2SeO3 solution was used as tracer solution. Dry density range of bentonite was from 0.8 to 1.4 ×103 kg/m3.
Results indicated that Se was strongly retained by the processes such as precipitation reaction with ferrous ions in bentonite. Se K-edge X-ray absorption near-edge structure (XANES) measurements were performed at the BL-11 beamline at SAGA Light Source, and the results revealed that the oxidation state of Se in the bentonite remained Se(IV)..
30. Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Daisuke Akiyama, Yusuke Irie, Hikaru Kozaki, Migration Behavior of Cesium Molybdate in Compacted Bentonite, Materials Research Society 2012, 2012.11.
31. Kazuya Idemitsu, Yaohiro Inagaki, Tatsumi Arima, Yoshihiko Matsuki, Masanao Kishimoto, Yoshiko Haruguchi, Yu Yamashita, Michitaka Sasoh, Migration of Iodine Solidified in Ettringite into Compacted Bentonite, Materials Issues in Nuclear Waste Management in the 21st Century, 2012.10.
32. 松木喜彦, 出光一哉, 秋山大輔, 入江祐介,稲垣八穂広, 有馬立身, ベントナイト中のヨウ素の移行挙動, 日本原子力学会「2012春の大会」, 2012.03.
33. 入江祐介, 出光一哉, 稲垣八穂広, 有馬立身,秋山大輔, 松木喜彦, 圧縮ベントナイト中におけるモリブデン酸セシウムの移行挙動, 日本原子力学会「2012春の大会」, 2012.03.
34. Yoshihiko MATSUKI, Kazuya IDEMITSU, Daisuke AKIYAMA, Yaohiro INAGAKI, Tatsumi ARIMA, Migration behavior of iodine in compacted bentonite, Global 2011, 2011.12.
35. Kazuya Idemitsu, Daisuke Akiyama, Yoshihiko Matsuki, Yusuke Irie, Yaohiro Inagaki, Tatsumi Arima, Migration Behaviour of Lanthanides in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method, Materials Research Society 2011, 2011.10.
36. 秋山大輔, 出光一哉, 松木喜彦, 入江祐介, 有馬立身, 稲垣八穂広, 電気化学的手法を用いた圧縮ベントナイト中におけるランタニドの移行挙動, 日本原子力学会「2011秋の大会」, 2011.09.
37. 出光一哉, 電気化学的手法による緩衝材中のプルトニウムの移行挙動研究, 平成22年度大洗研究会, 2010.11.
38. 仁科匡弘、有馬立身、稲垣八穂広、出光一哉、佐藤勇, MDシミュレーションによるアクチニドおよび酸素イオンの粒界拡散挙動評価, 日本原子力学会「2010秋の大会」, 2010.09.
39. 村田顕彦、出光一哉、有馬立身、稲垣八穂広, ゾルーゲル法を用いた複合燃料の製造法の開発:内部ゲル化法とアルギン酸ナトリウム法の比較, 日本原子力学会「2010秋の大会」, 2010.09.
40. 松木喜彦、出光一哉、稲垣八穂広、有馬立身、秋山大輔、春口佳子、山下雄生、三倉通孝、金子昌章, 還元環境下でのエトリンガイト中のヨウ素の化学変化測定, 日本原子力学会「2010秋の大会」, 2010.09.
41. 多田雅彦、稲垣八穂広、出光一哉、有馬立身、加藤修、桜木智史, 還元雰囲気のおけるFeCl2水溶液中でのAgI溶解の温度依存性, 日本原子力学会「2010秋の大会」, 2010.09.
42. 酒谷圭一、牧垣光、稲垣八穂広、出光一哉、有馬立身、三ツ井誠一郎、野下健司, マイクロリアクタ流水試験によるガラス固化体の溶解挙動とpHとの関係, 日本原子力学会「2010秋の大会」, 2010.09.
43. 秋山大輔、出光一哉、松木喜彦、稲垣八穂広、有馬立身, 電気化学的手法を用いた圧縮ベントナイト中におけるアルカリ土類金属イオンの移行挙動, 日本原子力学会「2010秋の大会」, 2010.09.
44. 秋山大輔、出光一哉、松木喜彦、稲垣八穂広、有馬立身, 電気化学的手法を用いた圧縮ベントナイト中におけるアルカリ土類金属イオンの移行挙動, 日本原子力学会「2010秋の大会」, 2010.09.
45. Kazuya Idemitsu, Daisuke Akiyama, Akira Eto, Yoshihiko Matsuki, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Alkali Earth Ions in Compacted Bentonite with Iron Corrosion Product Using Electrochemical Method, Materials Research Society 2010, 2010.04.
46. 出光一哉、秋山大輔、有馬立身、稲垣八穂広、春口佳子、山下雄生、金子昌章, XANESによるセメント中のヨウ素の測定, 日本原子力学会「2010春の年会」, 2010.03.
47. 秋山大輔、出光一哉、有馬立身、稲垣八穂広, 電位勾配下におけるベントナイト中のアルカリ金属の移行挙動, 日本原子力学会「2009秋の大会」, 2009.09.
48. Kazuya Idemitsu, Hirotomo Ikeuchi, Daisuke Akiyama, Yaohiro Inagaki, Tatsumi Arima, Migration Behavior of Potassium and Rubidium in Compacted Bentonite Under Reducing Condition with Iron Corrosion Product, Materials Research Society 2009, 2009.05.
学会活動
所属学会名
American Ceramic Society
Materials Research Society
日本原子力学会
学協会役員等への就任
2015.10~2016.09, 日本原子力学会九州支部, 2016秋の大会現地委員長.
2014.05~2015.05, 日本原子力学会九州支部, 支部長.
2013.05~2014.05, 日本原子力学会九州支部, 副支部長.
2013.05~2015.05, 日本原子力学会, 理事(部会等担当).
2008.03~2009.03, 日本原子力学会バックエンド部会, 部会長.
2006.05~2008.05, 日本原子力学会九州支部, 幹事(監査).
2003.06~2005.06, 日本原子力学会, 広報委員.
1999.06~2003.05, 日本原子力学会, 編集委員.
学会大会・会議・シンポジウム等における役割
2022.03.16~2022.03.18, 日本原子力学会「2022春の年会」3/17 2H13-17(核種移行・収着3), 座長(Chairmanship).
2022.03.16~2022.03.18, 日本原子力学会「2022春の年会」3/17 バックエンド企画セッション, 座長(Chairmanship).
2021.10.26~2021.10.29, MRS2021, 座長(Chairmanship).
2021.09.08~2021.09.10, 日本原子力学会「2021秋の大会」9/9 2C10-15(事故炉の廃止措置技術1), 座長(Chairmanship).
2018.11.26~2012.11.29, MRS2018, 座長(Chairmanship).
2016.06.27~2016.06.27, Goldschmidt2016, 座長(Chairmanship).
2015.09.09~2015.09.11, 日本原子力学会「2015秋の大会」9/11 H47ーH51(TRU廃棄物), 座長(Chairmanship).
2015.10.04~2015.10.07, Materials Science & Technology 2015, 座長(Chairmanship).
2014.09.08~2014.09.10, 日本原子力学会「2014秋の大会」, 座長(Chairmanship).
2014.08.27~2014.08.28, IUMRS-ICA 国際会議 D-9 Scientific Basis of the Nuclear Fuel Cycle II, 座長(Chairmanship).
2014.03.26~2014.03.28, 日本原子力学会「2014春の年会」, セッション「処分場評価・概念検討」座長.
2013.03.26~2014.03.28, 日本原子力学会「2013春の年会」, セッション「Cs吸着」座長.
2012.11.26~2012.11.30, MRS2012, 座長(Chairmanship).
2011.12.11~2011.12.16, GLOBAL 2011, 座長(Chairmanship).
2011.08.04~2011.08.05, 日本原子力学会バックエンド部会「2011夏期セミナー」, 座長(Chairmanship).
2010.09.16~2010.09.16, 日本原子力学会「2010秋の大会」, 特別セッション「原子力システム研究開発事業への期待ー事業の魅力向上に向けてー」座長.
2009.09.02~2009.09.02, 日本土木学会「2009秋の大会」, 特別セッションパネラー.
2009.03.23~2009.03.25, 日本原子力学会「2009春の年会」, バックエンド部会/再処理リサイクル部会合同部会セッション司会.
2008.09.04~2008.09.06, 日本原子力学会「2008秋の大会」, 座長(Chairmanship).
2008.03.26~2008.03.28, 日本原子力学会「2008春の年会」, 座長(Chairmanship).
2007.09.27~2007.09.29, 日本原子力学会「2007秋の大会」, 座長(Chairmanship).
2004.03.29~2004.03.31, 日本原子力学会「2004春の年会」, 座長(Chairmanship).
2003.09.24~2003.09.26, 日本原子力学会「2003秋の大会」, 座長(Chairmanship).
2003.03.27~2003.03.29, 日本原子力学会「2003春の年会」, 座長(Chairmanship).
2002.09.14~2002.09.16, 日本原子力学会「2002秋の大会」, 座長(Chairmanship).
2002.03.27~2002.03.29, 日本原子力学会「2002春の年会」, 座長(Chairmanship).
2001.03.27~2001.03.29, 日本原子力学会「2001春の年会」, 座長(Chairmanship).
2000.09.15~2000.09.18, 日本原子力学会「2000秋の大会」, 座長(Chairmanship).
2000.03.28~2000.03.30, 日本原子力学会「2000春の年会」, 座長(Chairmanship).
1999.09.28~1999.09.30, Global 1999, 座長(Chairmanship).
1999.09.10~1999.09.12, 日本原子力学会「1999秋の大会」, 座長(Chairmanship).
1999.03.22~1999.03.24, 日本原子力学会「1999春の年会」, 座長(Chairmanship).
1998.09.28~1998.09.30, 日本原子力学会「1998秋の大会」, 座長(Chairmanship).
1998.03.26~1998.03.28, 日本原子力学会「1998春の年会」, 座長(Chairmanship).
2017.04.24~2017.04.28, ICAPP2017, 組織委員.
2016.06.26~2016.06.30, Goldshmidt2016, オーガナイザー(シンポジウム10i).
2016.09.07~2016.09.09, 原子力学会2016秋の大会, 現地委員長.
2015.10.04~2015.10.08, MS&T'15, オーガナイザー(Materials Issue in Nuclear Waste Management in the 21st century).
2014.08.27~2014.08.28, IUMRS-ICA2014, オーガナイザー(シンポジウムD9).
2014.06.15~2014.06.20, CIMTEC 2014, プログラム委員.
2012.11.29~2012.12.05, MRS2012 Scientific Basis for Nuclear Waste Management XXXVI, 運営委員.
2011.12.11~2011.12.17, Global2011, 運営委員.
2011.09.21~2009.09.21, 原子力学会秋の大会バックエンド部会企画セッション, パネラー.
2009.07.29~2009.07.30, 原子力学会バックエンド部会夏期セミナー, パネラー.
2008.07.31~2008.08.01, 原子力学会バックエンド部会夏期セミナー, パネルディスカッション司会.
学会誌・雑誌・著書の編集への参加状況
1999.06~2005.12, 日本原子力学会/英文誌, 国内, 査読委員.
1999.06~2003.05, 日本原子力学会/英文誌, 国内, 編集委員.
学術論文等の審査
年度 外国語雑誌査読論文数 日本語雑誌査読論文数 国際会議録査読論文数 国内会議録査読論文数 合計
2020年度
2019年度
2018年度
2017年度
2016年度
2015年度
2014年度 10 
2013年度 13 
2012年度
2011年度
2010年度
2009年度
2008年度
2006年度
2005年度
2004年度
2003年度
2002年度
2001年度
2000年度
1999年度
1998年度
その他の研究活動
海外渡航状況, 海外での教育研究歴
Materials Research Society2019, Austria, , 2019.10~2019.10.
Materials Research Society2018, UnitedStatesofAmerica, , 2018.11~2018.11.
International Conference on Ceramic materials and Components for Energy and Environmental Applications(CMCEE-12), Singapore, , 2018.07~2018.07.
Materials Research Society, Australia, , 2017.10~2017.11.
Materials Research Society, UnitedStatesofAmerica, , 2016.11~2016.12.
Materials Research Society, France, , 2015.11~2015.11.
Material Science and Technology conference ( MS&T'15), UnitedStatesofAmerica, , 2015.10~2015.10.
Materials Research Society, UnitedStatesofAmerica, , 2014.11~2014.12.
Materials Research Society, Spain, , 2013.09~2013.10.
Materials Research Society, UnitedStatesofAmerica, , 2012.11~2012.11.
Material Science and Technology conference ( MS&T'12) , UnitedStatesofAmerica, , 2012.10~2012.10.
Materials Research Society, Argentina, , 2011.10~2011.10.
Materials Research Society, UnitedStatesofAmerica, , 2010.04~2010.04.
Materials Research Society, Russia, , 2009.05~2009.05.
Materials Research Society, UnitedStatesofAmerica, , 2008.12~2008.12.
Kernkraftwerk Gösgen-Däniken AG(ゲスゲン・デニケン電力会社), TVO、ポシヴァ社, EC(欧州委員会), EDF(フランス電力)、アレバ社、米国NEI、DOE, Switzerland, Finland, ルクセンブルグ, フランス、米国, 2007.11~2007.11.
Materials Research Society, Germany, UnitedKingdom, 2007.09~2007.09.
Materials Research Society, UnitedStatesofAmerica, 2006.11~2006.11.
アイダホ国立研究所(旧ANL-West), オークリッジ(ガス拡散濃縮施設), ICONE-14(マイアミ), UnitedStatesofAmerica, 2006.07~2006.07.
Materials Research Society, Belgium, 2005.09~2005.09.
Materials Research Society, UnitedStatesofAmerica, 2004.04~2004.04.
Materials Research Society, Sweden, 2003.06~2003.06.
Materials Research Society, UnitedStatesofAmerica, 2002.12~2002.12.
Materials Research Society, UnitedStatesofAmerica, 2001.12~2001.12.
Paul Scherrer Institute, DWE, Switzerland, Germany, Austria, 2001.08~2001.09.
University of California, Berkeley, UnitedStatesofAmerica, 2000.04~2000.04.
Materials Research Society, UnitedStatesofAmerica, 1999.12~1999.12.
輻射防護研究所, China, 1999.09~1999.09.
Materials Research Society, UnitedStatesofAmerica, 1998.11~1998.11.
Paul Scherrer Institute, Switzerland, 1998.10~1998.10.
Paul Scherrer Institute, Switzerland, 1996.10~1997.10.
外国人研究者等の受入れ状況
2016.10~2016.03, 1ヶ月以上, 中国輻射防護研究院(CIRP), China, 文部科学省.
2016.04~2016.09, 1ヶ月以上, Ninh Thuan Nuclear Power Projects Management Board (EVNNPB), Vietnam, 文部科学省.
2015.10~2016.02, 1ヶ月以上, インドネシア原子力庁(BATAN) 放射性廃棄物技術センター(CRWT), Indonesia, 文部科学省.
2011.10~2012.03, 1ヶ月以上, バングラデシュ原子力委員会(BAEC) 原子力科学技術研究所(INST), Bangladesh, 文部科学省.
受賞
バックエンド部会論文賞, 日本原子力学会バックエンド部会, 2015.03.
Best Paper Award, The American Ceramic Society, Nuclear and Environmental Technology Division, 2013.11.
Best Poster Award, Materials Research Society, Scientific Basis for Nuclear Waste Management XXXVII, 2013.10.
研究資金
科学研究費補助金の採択状況(文部科学省、日本学術振興会)
2012年度~2015年度, 基盤研究(S), 分担, 福島原発事故で発生した廃棄物の合理的な処理・処分システム構築に向けた基盤研究.
2007年度~2009年度, 基盤研究(B), 代表, 電位勾配下におけるベントナイト中のイオンの移動挙動に関する研究.
競争的資金(受託研究を含む)の採択状況
2006年度~2009年度, , 代表, セメント材料の長期変質評価手法に関する研究調査.
2008年度~2009年度, 原子力コア人材育成事業, 代表, 原子力コア人材育成事業
九州大学における核燃料サイクル工学に関する実験・演習の充実.
2006年度~2007年度, , 代表, セメント材料の劣化に関する研究.
2005年度~2006年度, , 代表, セメント材料の劣化に関する研究.
2004年度~2005年度, , 代表, セメント材料の劣化に関する研究.
2001年度~2003年度, 核燃料サイクル機構先行基礎研究, 代表, オーバパック材腐食生成物が緩衝材性能に及ぼす影響に関する研究.
2000年度~2002年度, 核燃料サイクル機構公募研究, 分担, ゾルゲル法を用いたCERMET燃料・固化体製造に関する研究.
共同研究、受託研究(競争的資金を除く)の受入状況
2019.10~2024.03, 分担, 「燃料デブリ分析のための超微量分析技術の開発」のうち、模擬燃料デブリの溶解挙動についての研究を行う。.
2012.08~2012.09, 代表, ホウ酸塩化合物の安定保持メカニズムの検討/結晶性の異なるホウ酸塩について、XAFSによる微細視野領域分析を実施し、ホウ素と他の元素間の結合状態を評価する。.
2009.08~2010.03, 代表, セメント系材料の長期変質評価手法に関する調査研究
−極微小領域での結晶構造確認手法の検討−.
2008.11~2009.03, 代表, セメント系材料の長期変質評価手法に関する調査研究
−極微小領域での結晶構造確認手法の検討−.
2006.11~2007.05, 代表, 人工バリア長期性能確証試験(その3)
−人工バリア相互影響確証試験−.
2006.02~2006.05, 代表, 人工バリア長期性能確証試験(その3)
−人工バリア相互影響確証試験−.
2005.02~2005.03, 代表, 人工バリア長期性能確証試験(その3)
−人工バリア相互影響確証試験−.
2004.02~2004.03, 分担, 人工バリア長期性能確証試験(その2)
−人工バリア相互影響確証試験−.
2003.02~2003.03, 分担, 人工バリア長期性能確証試験(その2)
−人工バリア相互影響確証試験−.

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pure2017年10月2日から、「九州大学研究者情報」を補完するデータベースとして、Elsevier社の「Pure」による研究業績の公開を開始しました。
 
 
九州大学知的財産本部「九州大学Seeds集」