Oral presentation

[1L01-03] Tritium Production and Environmental Behavior

Wed. Sep 6, 2023 10:00 AM - 10:50 AM Room L (ES Bildg. 3F ES033)

Chair:Yu Tachibana(Nagaoka Univ. of Tech.)

10:00 AM - 10:15 AM

[1L01] Study on T production using high-temperature gas-cooled reactor for fusion reactors ~Structure of the irradiation test module and experimental method~

*Kanta Kitagawa¹, Hideaki Matsuura¹, Hiromi Kawai¹, Kazunari Katayama¹, Teppei Otsuka², Etsuo Otsuka³, Shigeaki Nakagawa³, Minoru Goto⁴, Kenji Tobita⁵, Satoshi Konishi⁶ (1. Kyushu Univ., 2. Kindai Univ., 3. JAEA, 4. Univ. of Fukui, 5. Tohoku Univ., 6. Kyoto fusioneering)

10:15 AM - 10:30 AM

[1L02] Experimental investigation of tritium release behavior from neutron irradiated LiAlO₂ with Zr for tritium production in high-temperature gas-cooled reactor

*Hiroki Isogawa¹, Kazunari Katayama¹, Hideaki Matsuura¹, Makoto Oya¹, Seiyo Kobayashi¹ (1. KYUSHU UNIVERSITY)

10:30 AM - 10:45 AM

[1L03] Evaluation of deuterium amount retained in water plant grown in heavy water

*Zonglin Yang¹, Kazunari Katayama¹, Yutaro Wada¹, Michael Ofotsu Portuphy¹, Kanta Asao¹ (1. Kyushu Univ.)

Time reserved for Chair （10:45 AM - 10:50 AM）

Oral presentation

[1L04-07] Separation and Recovery Processes

Wed. Sep 6, 2023 10:50 AM - 12:00 PM Room L (ES Bildg. 3F ES033)

Chair:Yuki Edao(QST)

10:50 AM - 11:05 AM

[1L04] Recovery of tritium from neutron-irradiated lithium by yttrium

*Kazunari Katayama¹, Junnosuke Haruta¹, Shota Katayama¹, Yuuka Mori², Makoto Oya¹, Makoto Oyaidzu³ (1. Eng. Sci. Kyushu Univ. , 2. Eng. Kyushu Univ., 3. QST)

11:05 AM - 11:20 AM

[1L05] Tritium continuous recovery from Liquid Lithium-Lead droplets -2

High extraction efficiency analysis

*Fumito Okino¹, Yukinori Hamaji ², Teruya Tanaka², Juro Yagi¹ (1. Institute of Advanced Energy, Kyoto University, 2. National Institute for Fusion Scienece)

11:20 AM - 11:35 AM

[1L06] Examination of costs for separating tritium discharged from nuclear facilities and refining it to helium-3

*Tadayuki Nakahama¹, Satoshi Seino¹, Takashi Nakagawa¹ (1. Osaka Univ.)

11:35 AM - 11:50 AM

[1L07] Effect of eluants on lithium isotope enrichment using chromatography

*Yu Tachibana¹, Tomasz Kalak², Masahiro Tanaka³ (1. Nagaoka Univ. of Tech., 2. Poznan University of Economics and Business, 3. NIFS)

Time reserved for Chair （11:50 AM - 12:00 PM）

Oral presentation

[1L08-11] Hydrogen Isotope Permeation

Wed. Sep 6, 2023 2:45 PM - 3:50 PM Room L (ES Bildg. 3F ES033)

Chair:Kazunari Katayama(Kyushu Univ.)

2:45 PM - 3:00 PM

[1L08] Hydrogen gas evolution during corrosion of the F82H steel at high temperature and pressure

*Teppei Otsuka¹, Koji Yuasa¹, Masahiro Konno¹, Motoki Nakajima², Yenjui Huang², Takashi Nozawa² (1. Kindai Univ., 2. QST)

3:00 PM - 3:15 PM

[1L09] Application of electrochemical techniques to hydrogen isotopes permeation phenomenon induced by water corrosion of the F82H steel

*Masato Konno¹, Teppei Otsuka², Motoki Nakajima³, Yenjui Huang³, Takashi Nozawa³ (1. Kindai Univ., 2. Kindai, 3. QST)

3:15 PM - 3:30 PM

[1L10] Hydrogen isotopes permeation through the interface between liquid Sn and metal substrates

(1) Hydrogen isotopes permeation through liquid Sn supported with a F82H steel substrate

*Yuya Ando¹, Ryo Hatano¹, Teppei Otsuka¹ (1. Kindai Univ.)

3:30 PM - 3:45 PM

[1L11] Hydrogen isotopes permeation through the interface between liquid Sn and metal substrates

(2) Effects of intermediate alloying layers at the interface between liquid Sn alloys and supporting metal substrates

*Ryo Hatano¹, Yuya Ando¹, Teppei Otsuka¹ (1. Kindai Univ)

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[1L12-14] Hydrogen Isotope Behavior

Wed. Sep 6, 2023 3:50 PM - 4:40 PM Room L (ES Bildg. 3F ES033)

Chair:Naoko Ashikawa(NIFS)

3:50 PM - 4:05 PM

[1L12] Effect of oxidation of co-existing metals in primary system on tritium permeation through Inconel 600 under high temperature, high pressure water environment

*Azusa Matsumoto¹, Yuji Hatano¹ (1. University of Toyama)

4:05 PM - 4:20 PM

[1L13] Characteristic of permeation through palladium alloy membrane for hydrogen separation under low partial pressure

*Yuki Edao¹ (1. QST)

4:20 PM - 4:35 PM

[1L14] Change in Tritium Release Behavior of advanced LiT₂iO₃-Li₄SiO₄ Mixed Ceramic Materials by neutron fluence

*Asahi Sanfukuji Sanfukuji¹, Qilai Zhou^2,1, Kobayashi Makoto³, Oya Yasuhisa¹ (1. Shizuoka Univ., 2. Wuhan University of Technology., 3. NIFS)

Time reserved for Chair （4:35 PM - 4:40 PM）

Oral presentation

[1L15-18] Tritium in DEMO/LHD/JET

Wed. Sep 6, 2023 4:40 PM - 5:45 PM Room L (ES Bildg. 3F ES033)

Chair:Teppei Otsuka(Kindai Univ.)

4:40 PM - 4:55 PM

[1L15] Tritium retention in gaps of first wall and divertor tiles used in JET-ITER like wall experiment

*Yuji Hatano¹, Suneui Lee¹, Suguru Masuzaki², Masayuki Tokitani², Yasuhisa Oya⁴, Naoko Ashikawa², Hirofumi Nakamura³, Takumi Hayashi³, Anna Widdowson⁶, Marek Rubel⁵ (1. Univ. of Toyama, 2. NIFS, 3. QST, 4. Shizuoka Univ., 5. KTH Royal Inst. of Tech., 6. CCFE)

4:55 PM - 5:10 PM

[1L16] Tritium retention in the first-wall and divertor tiles during the deuterium plasma campaigns in LHD

*Suguru Masuzaki^1,2, Miyuki Yajima^1,2, Masahiro Tanaka¹, Gen Motojima^1,2, Tomohiro Morisaki^1,2, Masayuki Tokitani^1,2, Teppei Otsuka³, Naoaki Yoshida⁴, Yasuhisa Oya⁵, Yuji Hatano⁶ (1. NIFS, 2. SOKENDAI, 3. KINDAI Univ., 4. KYUSHU Univ., 5. SHIZUOKA Univ., 6. Univ. TOYAMA)

5:10 PM - 5:25 PM

[1L17] Scenario of tritium decontamination on plasma-facing components in Fusion DEMO

*Naoko Ashikawa^1,2, Yuji Torikai³, Kazuaki Kasai³, Yoji Someya⁴, Akira Taguchi⁵, Kiyohiro Yabuuchi⁶ (1. NIFS, 2. SOKENDAI, 3. Ibaraki Univ., 4. QST, 5. U. of Toyama, 6. Kyoto Univ.)

5:25 PM - 5:40 PM

[1L18] Integrating the tritium fuel cycle for fusion energy demonstration plant (UNITY-2)

Outline and Development Plan for UNITY-2

*Daiki Kikuchi¹, Yoshinao Matsunaga¹, Yoshifumi Kume¹, Colin Baus¹, Richard Pearson¹, Bibake Uppal¹, Kiyoshi Seko¹, Satoshi Konishi¹ (1. Kyoto Fusioneering)

Time reserved for Chair （5:40 PM - 5:45 PM）

Sessions

VI. Fusion Energy Engineering » 601-3 Tritium Science and Technology (Fuel Recovery and Refining, Measurement, Iisotope Effect, Safe Handling)

[1L01-03] Tritium Production and Environmental Behavior

[1L01] Study on T production using high-temperature gas-cooled reactor for fusion reactors ~Structure of the irradiation test module and experimental method~

[1L02] Experimental investigation of tritium release behavior from neutron irradiated LiAlO₂ with Zr for tritium production in high-temperature gas-cooled reactor

[1L03] Evaluation of deuterium amount retained in water plant grown in heavy water

[1L04-07] Separation and Recovery Processes

[1L04] Recovery of tritium from neutron-irradiated lithium by yttrium

[1L05] Tritium continuous recovery from Liquid Lithium-Lead droplets -2

High extraction efficiency analysis

[1L06] Examination of costs for separating tritium discharged from nuclear facilities and refining it to helium-3

[1L07] Effect of eluants on lithium isotope enrichment using chromatography

[1L08-11] Hydrogen Isotope Permeation

[1L08] Hydrogen gas evolution during corrosion of the F82H steel at high temperature and pressure

[1L09] Application of electrochemical techniques to hydrogen isotopes permeation phenomenon induced by water corrosion of the F82H steel

[1L10] Hydrogen isotopes permeation through the interface between liquid Sn and metal substrates

(1) Hydrogen isotopes permeation through liquid Sn supported with a F82H steel substrate

[1L11] Hydrogen isotopes permeation through the interface between liquid Sn and metal substrates

(2) Effects of intermediate alloying layers at the interface between liquid Sn alloys and supporting metal substrates

[1L12-14] Hydrogen Isotope Behavior

[1L12] Effect of oxidation of co-existing metals in primary system on tritium permeation through Inconel 600 under high temperature, high pressure water environment

[1L13] Characteristic of permeation through palladium alloy membrane for hydrogen separation under low partial pressure

[1L14] Change in Tritium Release Behavior of advanced LiT₂iO₃-Li₄SiO₄ Mixed Ceramic Materials by neutron fluence

[1L15-18] Tritium in DEMO/LHD/JET

[1L15] Tritium retention in gaps of first wall and divertor tiles used in JET-ITER like wall experiment

[1L16] Tritium retention in the first-wall and divertor tiles during the deuterium plasma campaigns in LHD

[1L17] Scenario of tritium decontamination on plasma-facing components in Fusion DEMO

[1L18] Integrating the tritium fuel cycle for fusion energy demonstration plant (UNITY-2)

Outline and Development Plan for UNITY-2

Authentication