Nov. 2022, プラズマ学融合学会賞 第27回技術進歩賞, 微粒子に蓄積するトリチウムの測定技術開発とJETで生成されたダスト分析への応用, 一般社団法人プラズマ核融合学会
芦川直子、大塚哲平、鳥養祐二、朝倉伸幸、増崎貴
Japan society

Nov. 2022, 第27回技術進歩賞, 微粒子に蓄積するトリチウムの測定技術開発とJETで生成されたダスト分析への応用, 一般社団法人プラズマ核融合学会
芦川直子、大塚哲平、鳥養祐二、朝倉伸幸、増崎貴
Japan society

Mar. 2021, 第3回日本原子力学会材料部会Best Figure賞, JET-ILWダストに対する燃焼法による残留トリチウム測定。酸化反応による錫燃焼の瞬間, 一般社団法人日本原子力学会
Japan society

〔Major achievements〕Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-LIKE WALL
Y. Torikai; G. Kikuchi; A. Owada1; S. Masuzaki; T. Otsuka; N. Ashikawa; M. Yajima; M. Tokitani; Y. Oya; S. E. Lee; Y. Hatano; N. Asakura; T. Hayashi; M. Oyaidzu; J. Likonen; A. Widdowson; M. Rubel and JET Contributors, Lead, Divertor tiles after JET-ILW campaigns and dust collected after JET-C and JET-ILW operation were examined by a set of complementary techniques (full combustion and radiography) to determine the total, specific and areal tritium activities, poloidal tritium distribution in the divertor and the presence of that isotope in individual dust particles. In the divertor tiles, the majority of tritium is detected in the surface region and, the areal activities in the ILW divertor are in the 0.5 - 12 kBq cm-2 range. The activity in the ILW dust is associated mainly with the presence of carbon particles being a legacy from the JET-C operation. The total tritium activities show significant differences between the JET operation with ILW and the earlier phase with the carbon wall (JET-C) indicating that tritium retention has been significantly decreased in the operation with ILW., IOP Publishing
Nuclear Fusion, 05 Dec. 2023, [Reviewed]

核融合プラズマ対向材の残留トリチウム測定法　　　　　　　　　　　　　　　
菊 地 絃 太 *, 芦 川 直 子 , 鳥 養 祐 二, Last, 核融合原型炉の実現に向け，核融合炉内に蓄積したトリチウムの定量測定法の確立が必須である.本研究で は，迅速かつ簡便なトリチウムの定量測定法としてオートクレーブ法を提案する.核融合プラズマ曝露試料に対 する測定手法を確立するため，大型ヘリカル装置(LHD)で曝露された試料中に含まれるトリチウムを実測した.,その結果，ボロンや炭素の堆積がある LHD 試料内から得られた残留トリチウム量は1.3-10.3 Bq であり， また全量測定が可能であることを示した.堆積層が十分に薄く無視できる試料では拡散モデルに基づく理論値と オートクレーブ法による測定値で放出挙動が一致したが，堆積層が形成されている試料では堆積の特徴の違いに より理論値と測定値で放出挙動が異なることを明らかにし，これは残留トリチウムが存在する深さに依存するこ とを示唆した., プラズマ・核融合学会
J. Plasma Fusion Research, Jun. 2023, [Reviewed]

Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments
S. Lee; Y. Hatano; S. Masuzaki; Y. Oya; M. Tokitani; M. Yajima; T. Otsuka; N. Ashikawa; Y. Torikai; N. Asakura; H. Nakamura; H. Kurotaki; T. Hayashi; T. Nozawa; A.M. Ito; J. Likonen; A. Widdowson; M. Rubel and JET Contributors, Tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall (ILW) during the first (ILW1), third (ILW3) and all three (ILW1-3) campaigns were examined and evaluated. Tritium was deposited on the surfaces inside the castellation grooves together with deuterium, beryllium, oxygen, carbon and small amounts of metallic impurities such as nickel, copper and tungsten. The tritium content after the ILW1 campaign was greater than after the ILW3 campaign. This is attributed to the steadily decreasing amount of carbon impurities in JET from campaign to campaign. The majority of tritium was retained in shallow regions in the grooves, up to 2 mm from the entrance to the gap. It was comparable on all sides of the castellation, i.e. no difference has been detected between the toroidal and poloidal gaps. Secondly, the tritium retention in the gaps was similar on all specimens independent of their position in the tokamak, while the retention on the plasma-facing surfaces clearly depended on the tile position. The tritium deposition patterns in the castellation were also compared with the deuterium distribution determined in earlier studies., IOP Science, IAEA
Nuclear Fusion, 08 Mar. 2023, [Reviewed]

Positron annihilation study of tungsten exposed to low-energy deuterium plasma
Tetsuya Hirade; Hikaru Furuta; Yuji Torikai; Yuki Fujimura; Koji Michishio, Positron annihilation lifetime spectroscopy (PALS) measurements by use of a positron source of 22Na were performed for the polycrystalline tungsten samples that were exposed to low-energy deuterium (D) plasma. The energy of D plasma was low and then it was expected that it would affect just the near-surface region. However, we obtained the longer mean positron annihilation lifetime in the tungsten samples exposed to the low-energy D plasma than the virgin tungsten sample. Moreover, the same longer values were obtained even on the other (no exposed) side of the samples, although the thickness of the samples was 1 mm or 2 mm. The elongation of the positron lifetime probably indicates defects formation in W. Ohsawa, et al. predicted that the high concentration hydrogen creates high concentration vacancy-hydrogen clusters by the first-principles calculations. We also performed positron annihilation age-momentum correlation (AMOC) measurements to know if there are some D’s at the positron trapping sites such as vacancies and found that some of the positrons annihilate with electrons in D., J-STAGE
JJAP Conference Proceedings, 13 Feb. 2023, [Reviewed]

An overview of tritium retention in dust particles from the JET-ILW divertor.
T Otsuka; S Masuzaki; N Ashikawa; Y Torikai; Y Hatano; M Tokitani; Y Oya; N Asakura; T Hayashi; H Tanigawa; Y Iwai; A Widdowson; M Rubel and JET Contributors,
Tritium (T) retention characteristics in dust collected from the divertor in JET with ITER-like wall (JET-ILW) after the third campaign in 2015–2016 (ILW-3) have been examined in individual dust particles by combining radiography (tritium imaging plate technique) and electron probe micro-analysis. The results are summarized and compared with the data obtained after the first campaign in 2011–2012 (ILW-1). The dominant component in ILW-1 dust was carbon (C) originating from tungsten-coated carbon fibre composite (CFC) tiles in JET-ILW divertor and/or legacy of C dust after the JET operation with carbon wall. Around 85% of the total tritium retention in ILW-1 dust was attributed to the C dust. The retention in tungsten (W) and beryllium (Be) dominated particles was 100 times smaller than the highest T retention in carbon-based particles. After ILW-3 the main component contributing to the T retention was W. The number of small W particles with T increased, in comparison to ILW-1, most probably by the exfoliation and fragmentation of W coatings on CFC tiles though T retention in individual W particles was smaller than in C particles. The detection of only very few Be-dominated dust particles found after ILW-1 and ILW-3 could imply stable Be deposits on the divertor tiles., IOP Publishing Ltd
Physica Scripta, Feb. 2022, [Reviewed]

Global distribution of tritium in JET with the ITER-like wall
S.E.Lee; Y. Hatano; M.Tokitani; S.Masuzaki; Y.Oya; T.Otsuka; N.Ashikawa; Y.Torikai; N.Asakura; H.Nakamura; K.Isobe; H.Kurotaki; D.Hamaguchi; T.Hayashi; A.Widdowson; S.Jachmich; J.Likonen; M.Rubel; JET contributors, ELSEVIA
Nuclear Materials and Energy, Mar. 2021, [Reviewed]

Investigation on tritium retention and surface properties on the first wall in the Large Helical Device
M. Yajima; S. Masuzaki; N. Yoshida; M. Tokitani; T. Otsuk; Y. Oya; Y. Torikai; G. Motojima; the LHD Experiment Groupa, ELSEVIA
Nuclear Materials and Energy, 20 Jan. 2021, [Reviewed]

Tritium retention in displacement-damaged tungsten exposed to deuterium-tritium gas mixture at elevated temperatures
V.Kh.Alimov; Y.Torikaia; Y.Hatano; T.Schwarz-Selingerd, W samples, previously irradiated with 20 MeV W ions at room temperature to a displacement-damage level of 0.23 displacements per atom (dpa) at the peak of displacements, were exposed to a deuterium-tritium (D2 ― DT ― T2) gas mixture with a tritium content of 6% at a total pressure of 1.2 kPa and temperatures of 773 K and 973 K for 3 h. The concentration of tritium retained in the displacement-damage zone of these W samples was determined by a method combining chemical etching and subsequent analysis of tritium in the etching solution using liquid scintillation counting (CE-LSC)., ELSEVIER
Fusion Engineering and Design, 18 Nov. 2020, [Reviewed]

Determination of retained tritium from ILW dust particles in JET
N. Ashikawa; Y. Torikai; N. Asakura; T. Otsuka; A. Widdowson; M. Rubel; M. Oyaizu; M. Hara; S. Masuzaki; K. Isobe; Y. Hatano; K. Heinola; A. Baron-Wiechec; S. Jachmich; T. Hayashi and JET
Nuclear Materials and Energy, Jan. 2020, [Reviewed]

Influence of plasma impurities on the fuel retention in tungsten
A. Kreter; D. Nishijima; R.P. Doerner; M. Freisinger; Ch. Linsmeier; Y. Martynova; S. Möller; M. Rasinski; M. Reinhart; A. Terra; Y. Torikai and B. UnterbergHayashi and JET Contributors
Nuclear Fusion, Jun. 2019

Effects of baking in deuterium atmosphere on tritium removal from tungsten
Yuji Nobuta; Yuji Hatano; Yuji Torikai; Masato Nakayama
Fusion Engineering and Design, Nov. 2018, [Reviewed]

Measurement of tritium in tungsten deposition layer by imaging plate technique after exposure to gaseous tritium
M. Noguchi; K. Katayama; Y. Torikai; N. Ashikawa; A. Taguchi; S. Fukada
Fusion Engineering and Design, Nov. 2017, [Reviewed]

The microstructure of tungsten exposed to D plasma with different impurities　　　　　　　　　　　　　　　
M. Rasinski; A. Kreter; Y. Torikai; Ch. Linsmeier
Nuclear Materials and Energy, Aug. 2017, [Reviewed]

Comparison of TEM and positron annihilation lifetime spectroscopy on tungsten exposed to mixed D plasmas
M. Rasinski; A. Kreter; Y. Torikai; G. P. Karwasz
European Microscopy Congress 2016, Dec. 2016, [Reviewed]

Desorption behavior of tritiated water from organic functionalized mesoporous silica
A. Taguchi; Y. Kato; R. Akai; Y. Torikai
Fusion Engineering and Design, Dec. 2016, [Reviewed]

Tritium desorption and tritium removal from tungsten pre-irradiated with helium
Y. Nobuta; Y. Hatano; Y. Torikai; M. Matsuyama; S. Abe; Y. Yamauchi
Fusion Engineering and Design, Jan. 2016, [Reviewed]

Tritium burning in inertial electrostatic confinement fusion facility
M. Ohnishi; Y. Yamamoto; H. Osawa; Y. Hatano; Y. Torikai; I. Murata; K. Kamakura; M. Onishi; K. Miyamoto; H. Konda; K. Masuda; E. Hotta
Fusion Engineering and Design, Nov. 2015, [Reviewed]

Gaseous tritium uptake by C deposition layer on tungsten
Y. Hamaji; H.T. Lee; Y. Torikai; K. Sugiyama; Y. Ueda
Journal of Nuclear Materials, Aug. 2015, [Reviewed]

Tritium release from SS316 under vacuum condition
Y. Torikai and R.-D. Penzhorn, Lead
Fusion Science and Technology, Apr. 2015, [Reviewed]

Measurement of Uptake and Release of Tritium by Tungsten
M. Nakayama; a; Y. Torikai; M. Saito; R. -D. Penzhorn; K. Isobe; T. Yamanishi; H. Kurishita
Fusion Science and Technology, Apr. 2015, [Reviewed]

Tritium Trapping on the Plasma Irradiated Tungsten Surface
Y. Torikai; V. Kh. Alimov; K. Isobe; M. Oyaidzu; T. Yamanishi; R.-D. Penzhorn; Y. Ueda; H. Kurishita; V. Philipps; A. Kreter; M. Zlobinski, Lead
Fusion Science and Technology, Apr. 2015, [Reviewed]

Tritium Removal from Tritiated Water by Organic Functionalized SBA-15
A. Taguchi; Y. Kato; R. Akai; Y. Torikai; M. Matsuyama
Fusion Science and Technology, Apr. 2015, [Reviewed]

Behavior of Tritium in the Vacuum Vessel of JT-60U
Y. Torikai; M. Saito; V. Alimov; N. Miya and Y. Ikeda
Fusion Science and Technology, Mar. 2015, [Reviewed]

Current status of nanostructured tungsten-based materials development
H. Kurishita; S. Matsuo; H. Arakawa; T. Sakamoto; S. Kobayashi; K. Nakai; H. Okano; H. Watanabe; N. Yoshida; Y. Torikai; Y. Hatano; T. Takida; M. Kato; A. Ikegaya; Y. Ueda; M. Hatakeyama; T. Shikama, IOP Science
Physica Scripta, 01 Apr. 2014, [Reviewed]

Surface erosion and modification of toughened, fine-grained, recrystallized tungsten exposed to TEXTOR edge plasma
Y. Ueda; M. Oya; Y. Hamaji; H. T. Lee; H. Kurishita; Y. Torikai; N. Yoshida; A. Kreter; J. W. Coenen; A. Litnovsky; V. Philipps, IOP Sience
Physica Scripta, 01 Apr. 2014, [Reviewed]

Tritium trapping behavior in tungsten pre-irradiated with D, He, Ar and N plasmas　　　　　　　　　　　　　　　
Y Hamaji; Y Torikai; H T Lee; Y Otsuka; Y Ueda, Tritium (T) trapping in tungsten after plasma exposure (deuterium (D), helium (He), nitrogen (N), argon (Ar)) was studied using an imaging plate technique. Specimens were exposed to D and T mixed gas at 77 and 573 K to distinguish T trapped at the outermost surface and several tens of nanometers, respectively. He followed by N, Ar and D plasma exposures resulted in the largest increase in T trapping. This was interpreted to result from He bubble layers that can increase the surface area by formation of pores connected to the surface and/or an increase in surface trapping sites. T exposure at 77 K was found to be a very useful method to observe plasma-induced changes to T trapping at the outermost surface., IOP Science
Physica Scripta, 01 Apr. 2014, [Reviewed]

Enrichment of tritiated water using mesoporous silica
A. Taguchi; Y. Kato; Y. Torikai; M. Matsuyama; S. Uchida
Microporous and Mesoporous Materials, 15 Sep. 2013, [Reviewed]

Tritium Interaction with Surface Layer and bulk of Type 316 Stainless Steel and Consequences of Aging
R.-D. Penzhorn; Y. Hatano; M. Matsuyama; Y. Torikai, Last, ANS
Fusion Since and Technology, Jul. 2013, [Reviewed]

Tritium loading study of tungsten pre-exposed to TEXTOR plasmas
Y. Torikai; A. Taguchi; M. Saito; R.-D. Penzhorn; Y. Ueda; H. Kurishita; K. Sugiyama; V. Philipps; A. Kreter; M. Zlobinski; TEXTOR team, Lead, Elsevia
Journal of Nuclear Materials, Jul. 2013, [Reviewed]

Deuterium retention in Toughened, Fine-Grained Recrystallized Tungsten
M. Oya; K. Uekita; H. T. Lee; Y. Ohtsuka; Y. Ueda; H. Kurishita; A. Kreter; J. W. Coenen; V. Philipps; S. Brezinsek; A. Litnovsky; K. Sugiyama; Y. Torikai, Last, Elsevia
Journal of Nuclear Materials, Jul. 2013, [Reviewed]

Melt-layer ejection and material changes of three different tungsten materials under high heat-flux conditions in the tokamak edge plasma of TEXTOR
J. W. Coenen; V. Philipps; S. Brezinsek; G. Pintsuk; I. Uytdenhouwen; M. Wirtz; A. Kreter; K. Sugiyama; H. Kurishita; Y. Torikai; Y. Ueda; U. Samm
NUCLEAR FUSION, Nov. 2011, [Reviewed]

Trapping and depth profile of tritium in surface layers of metallic materials
M. Matsuyama; Z. Chen; K. Nisimura; S. Akamaru; Y. Torikai; Y. Hatano; N. Ashikawa; Y. Oya; K. Okuno; T. Hino
Journal of Nuclear Materials, 01 Oct. 2011, [Reviewed]

Depth profiling of tritium in bulk tungsten divertor tiles from JET with metal walls: tritium quantification and surface decontamination　　　　　　　　　　　　　　　
Y. Torikai; Y. Obata; K. Kasai; R. Nishida; S. Oono; K. Mizobuchi; N. Ashikawa; S.Masuzaki; M. Yajima; A. Owada; K. Isobe; T. Hayashi; H. Nakamura; Y. Sugimoto; M. Rubel; A. Widdowson
20TH INTERNATIONAL CONFERENCE ON PLASMA-FACING MATERIALS AND COMPONENT FOR FUSION APPLICATIONS
20250519, 20250523

JET-ダイバータタイルのトリチウム分析　　　　　　　　　　　　　　　
鳥養祐二、菊地絃太、○大和田篤志、増崎貴、大塚哲平、芦川直子、矢嶋美幸、時谷政行、大矢恭久、S.E.Lee、波多野雄治、朝倉伸行、林巧、小柳津誠、J.Likonen、A.Widdowson、M.Rubel
日本放射化学会第66回討論会(2022), 16 Sep. 2022, 日本放射化学会
20220915, 20220917

Development of a rapid measurement method for environmental tritium concentratio n,( Rapid screening method for tritium concentration in fis h　　　　　　　　　　　　　　　
細根 孟留、 南 場 大 輝、川上 智 彦、柿内 秀 樹、鳥養 祐 二
日本原子力学会2022年秋の大会, 08 Sep. 2022, 日本原子力学会
20220907, 20220909

Development of a rapid measurement method for environmental tritium concentration (3) Simplification and acceleration of environmental tritium measurement　　　　　　　　　　　　　　　
南場 大輝、細根 孟留、川上 智彦、柿内 秀樹、鳥養 祐二
日本原子力学会2022年秋の大会, 08 Sep. 2022, 日本原子力学会
20220907, 20220909

Tritium Issues in DEMO
鳥養祐二
第14回核融合エネルギー連合講演会, 08 Jul. 2022, プラズマ・核融合学会、日本原子力学会
20220707, 20220708

〔Major achievements〕海水中トリチウムの  測定法　　　　　　　　　　　　　　　
鳥養 祐二; 本間 駿太
第3回 日本放射線安全管理学会 日本保健物理学会 合同大会, 01 Dec. 2021
20211201, 20211203

Tritium retention in dust particles and divertor tiles of JET operated with the ITER-Like Wall　　　　　　　　　　　　　　　
Y. TORIKAI; G. KIKUCHI; A. OWADA; S. MASUZAKI; T. OTSUKA; N. ASHIKAWA; M. YAJIMA; M. TOKITANI; Y. OYA; S. E. LEE; Y. HATANO; N. ASAKURA; T. HAYASHI; M. OYAIDZU; A. WIDDOWSON; M. RUBEL and JET Contributors
28th IAEA Fusion Energy Conference, 14 May 2021
20210510, 20210515

核融合炉材料からの大気圧下でのトリチウムの放出　　　　　　　　　　　　　　　
鳥養祐二
プラズマ・核融合学会 第37回年会, 02 Dec. 2020

原型炉のトリチウム管理基準の考え方　　　　　　　　　　　　　　　
鳥養祐二
プラズマ核融合学会 第36回年会, 30 Nov. 2019
20191129, 20191202

Apr. 2016 - Present, 日本保健物理学会

Apr. 2001 - Present, プラズマ・核融合学会

Apr. 1964 - Present, 日本原子力学会

放射線とトリチウムの知識の習熟を基盤とした原子力規制人材育成　　　　　　　　　　　　　　　
Aug. 2023 - Mar. 2028

プラズマ対向壁への水素同位体の蓄積量の定量手法の開発と定量評価　　　　　　　　　　　　　　　
核融合科学研究所
Apr. 2023 - Mar. 2024

魚介類トリチウム濃度の迅速測定法に関するフィジビリティスタディ　　　　　　　　　　　　　　　
国立研究開発法人日本原子力研究開発機構
Jun. 2022 - Mar. 2023

魚中のトリチウム濃度測定法の簡素化・最適化　　　　　　　　　　　　　　　
Apr. 2022 - Mar. 2023

LHD真空容器内への水素同位体の蓄積量の定量手法の開発と定量評価　　　　　　　　　　　　　　　
Apr. 2022 - Mar. 2023

核融合実現に向けたトリチウム諸課題の検討　　　　　　　　　　　　　　　
Apr. 2022 - Mar. 2023

Investigation of tritium decontamination method under the vacuum condition for fusion reactors
Grant-in-Aid for Scientific Research (C)
National Institute for Fusion Science
01 Apr. 2018 - 31 Mar. 2022

Measurement of Hydrogen Isotope trapping on inside materials of LHD　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

Effective tritium removal under vacuum conditions　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

Tritium Transport in Fusion Reactor Materials　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

Evaluation of multi hydrogen isotope transfer behavior on plasma driven permeation for plasma facing materials　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

Workshop on plasma-wall interactions in LHD　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

Behavior, function and perspective of hydrogen isotope　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

核融合実現に向けたトリチウム諸課題の検討　　　　　　　　　　　　　　　
Apr. 2021 - Mar. 2022

JET ILW実験におけるプラズマ対向機器表面およびダストのトリチウム蓄積特性研究　　　　　　　　　　　　　　　
Jun. 2021 - Jan. 2022

Tritium bioeffects research for establishing social consensus on the disposal of tritiated water by oceanic discharge
Grant-in-Aid for Scientific Research (B)
Ibaraki University
01 Apr. 2016 - 31 Mar. 2021

Hydrogen isotope exchange on metaric plasma facing walls　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Evaluation of tritium tasks in DEMO　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Tritium Transport in Fusion Reactor Materials　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Tritium behavior in a secondary cooling system in a fusion DEMO reactor　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Evaluation of multi hydrogen isotope transfer behavior on plasma driven permeation for plasma facing materials　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Workshop on plasma-wall interactions in LHD　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

Measurement of hydrogen isotope inventory in inside materials of LHD　　　　　　　　　　　　　　　
Apr. 2020 - Mar. 2021

JET ILW実験におけるプラズマ対向機器表面およびダストのトリチウム蓄積特性研究　　　　　　　　　　　　　　　
Jun. 2020 - Jan. 2021

Management of Interdisciplinary study of tritium accepted in general public
Grant-in-Aid for Challenging Exploratory Research
01 Apr. 2015 - 31 Mar. 2017

Estimation of tritium accumulation in tungsten and its application for ITER divertor
Grant-in-Aid for Scientific Research (B)
University of Toyama
01 Apr. 2012 - 31 Mar. 2015

TRITIUM PERMEATION, CONTAMINATION AND DECONTAMINATION
Grant-in-Aid for Scientific Research on Priority Areas
University of Toyama
2007 - 2011

Research and development of a functional material with low adsorption and solubility of tritium for fusion systems.
Grant-in-Aid for Scientific Research (C)
University of Toyama
2007 - 2009

Construction of the standard system for absolute measurement of tritium
Grant-in-Aid for Scientific Research (A)
University of Toyama
2003 - 2005

Tracking of tritium trapped on/in high-Z materials by BIXS
Grant-in-Aid for Scientific Research (B)
TOYAMA UNIVERSITY
2001 - 2002

水素吸蔵合金電極を用いたトリチウム水のトリチウム回収法の開発
奨励研究(A)
富山大学
2000 - 2001

NHK取材　　　　　　　　　　　　　　
coverage_cooperation
NHK, 26 May 2023

原子力産業新聞取材　　　　　　　　　　　　　　
coverage_cooperation
原子力産業新聞, 19 May 2023

原子力産業新聞取材　　　　　　　　　　　　　　
coverage_cooperation
原子力産業新聞, 12 May 2023

NHK取材　　　　　　　　　　　　　　
coverage_cooperation
NHK, 26 Apr. 2023

原子力産業新聞取材　　　　　　　　　　　　　　
coverage_cooperation
原子力産業新聞, 20 Apr. 2023

共同通信社取材　　　　　　　　　　　　　　
coverage_cooperation
共同通信社, 19 Apr. 2023

読売新聞取材　　　　　　　　　　　　　　
coverage_cooperation
読売新聞, 14 Apr. 2023

読売新聞取材　　　　　　　　　　　　　　
coverage_cooperation
読売新聞, 12 Apr. 2023

第8回 ALPS処理水に係る海域モニタリング専門家会議　　　　　　　　　　　　　　
others
環境省, 24 Mar. 2023

環境省との打合せ　　　　　　　　　　　　　　
others
20 Mar. 2023

第58回RI・放射線利用促進セミナー　　　　　　　　　　　　　　
lecturer
中部原子力懇話会, 10 Feb. 2023

第7回 ALPS処理水に係る海域モニタリング専門家会議　　　　　　　　　　　　　　
others
環境省, 07 Feb. 2023

環境省との打合せ　　　　　　　　　　　　　　
others
31 Jan. 2023

第6回 ALPS処理水に係る海域モニタリング専門家会議　　　　　　　　　　　　　　
others
環境省, 14 Dec. 2022

環境省との打合せ　　　　　　　　　　　　　　
others
25 Nov. 2022

資源エネルギー庁との打合せ　　　　　　　　　　　　　　
others
01 Nov. 2022

第1回 ALPS処理水モニタリングシンポジウム　　　　　　　　　　　　　　
panelist
経済産業省, 25 Oct. 2022

資源エネルギー庁との打合せ　　　　　　　　　　　　　　
others
14 Oct. 2022

第1回 ALPS処理水モニタリングシンポジウム　　　　　　　　　　　　　　
panelist
経済産業省, 09 Sep. 2022

環境省との打合せ　　　　　　　　　　　　　　
others
01 Sep. 2022

資源エネルギー庁との打合せ　　　　　　　　　　　　　　
others
21 Jul. 2022

環境省との打合せ　　　　　　　　　　　　　　
others
10 Jun. 2022

資源エネルギー庁との打合せ　　　　　　　　　　　　　　
others
09 Jun. 2022

女川町議会原発対策特別委員会　　　　　　　　　　　　　　
lecturer
女川町議会, 09 Jun. 2021

ゴジてれChu！　　　　　　　　　　　　　　
appearance
福島中央テレビ, ゴジてれChu！, 18 Mar. 2020

ひるおび　　　　　　　　　　　　　　
appearance
ＴＢＳテレビ, ひるおび, 03 Oct. 2019

NEWS every　　　　　　　　　　　　　　
appearance
日本テレビ, NEWS every, 03 Oct. 2019

深層NEWS　　　　　　　　　　　　　　
appearance
日本テレビ, 深層NEWS, 26 Sep. 2019

ミヤネ屋　　　　　　　　　　　　　　
appearance
読売テレビ, ミヤネ屋, 25 Sep. 2019

サタデーステーション　　　　　　　　　　　　　　
appearance
テレビ朝日, サタデーステーション, 21 Sep. 2019

トリチウムの迅速測定　　　　　　　　　　　
NHK, NHK NEWS おはよう日本, 08 Aug. 2023, Media report

リスクを見つめる トリチウム水道水にも　　　　　　　　　　　
読売新聞, 27 Jun. 2023, Paper

韓国で塩"品切れ"背景に「雨」と「原発」福島原発の処理水放出への”不安”　　　　　　　　　　　
日本テレビ, ニュースゼロ, 21 Jun. 2023, Media report

ゴジてれChu！　　　　　　　　　　　
福島中央テレビ, ゴジてれChu！, 18 Mar. 2020, Media report

ひるおび　　　　　　　　　　　
ＴＢＳテレビ, ひるおび, 03 Oct. 2019, Media report

NEWS every　　　　　　　　　　　
日本テレビ, NEWS every, 03 Oct. 2019, Media report

深層NEWS　　　　　　　　　　　
日本テレビ, 深層NEWS, 26 Sep. 2019, Media report

ミヤネ屋　　　　　　　　　　　
読売テレビ, ミヤネ屋, 25 Sep. 2019, Media report

サタデーステーション　　　　　　　　　　　
テレビ朝日, サタデーステーション, 21 Sep. 2019, Media report