Oral Presentation

[3F01-06] radionuclide separation and recovery

Mon. Mar 28, 2016 9:30 AM - 11:10 AM Room F (Lecture Rooms B B201)

Chair: Kitatsuji Yoshihiro (JAEA)

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9:30 AM - 9:45 AM

[3F01] R&D of MA separation processes for P&T system using ADS

(6)Development of MA recovery process with TDdDGA

＊Tatsuro Matsumura¹, Hideya Suzuki¹, Yasuhiro Tsubata¹, Mitsunobu Shibata¹, Tatsuya Kurosawa¹, Tomohiro Kawasaki¹, Hiroshi Sagawa¹ (1.Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[3F02] R&D of MA separation processes for P&T system using ADS

(7)Examination of Novel Extractants for MA separation

＊Hideya Suzuki¹, Yasuhiro Tsubata¹, Mitsunobu Shibata¹, Tatsuya Kurosawa ¹, Tomohiro Kawasaki¹, Hiroshi Sagawa¹, Tatsuro Matsumura¹ (1.Japan Atomic Energy Agency)

10:00 AM - 10:15 AM

[3F03] EXAFS analysis of europium in various absorbents

＊Haruaki Matsuura¹, Atsushi Nezu², Shimpei Ono³, Tsuyoshi Arai³, Sou Watanabe⁴, Yuichi Sano⁴, Masayuki Takeuchi⁴ (1.Tokyo City University, 2.Tokyo Institute of Technology, 3.Shibaura Institute of Technology, 4.Japan Atomic Energy Agency)

10:15 AM - 10:30 AM

[3F04] Separation and recovery of soft metal ions by Copolymer Gel-Silica Composite with
High TPEN Content for Gel-liquid Extraction Process

＊Takuya kawamura¹, Kenji Takeshita¹ (1.Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology)

10:30 AM - 10:45 AM

[3F05] Radiolysis of adsorbent for the extraction chromatography technology

＊Sou Watanabe¹, Yuichi Sano¹, Ryoya Ishigami² (1.JAEA, 2.WERC)

10:45 AM - 11:00 AM

[3F06] Research on solubility of plutonium silicate in nitric acid solution using lanthanides as surrogates for plutonium

＊Yusho Matsumoto¹, Tatsumi Arima¹, Kazuya Idemitsu¹, Yaohiro Inagaki¹, Masafumi Tanigawa², Yoshiyuki Kato², Tsutomu Kurita² (1.Kyushu University Graduate School, 2.Japan Atomic Energy Agency)

Time reserved for Chair （11:00 AM - 11:10 AM）

Oral Presentation

[3F07-09] high-level liquid waste and-or glassification

Mon. Mar 28, 2016 11:10 AM - 12:00 PM Room F (Lecture Rooms B B201)

Chair: Uozumi Koichi (CRIEPI)

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11:10 AM - 11:25 AM

[3F07] Evaluation of Corrosion in the equipment containing High level radioactive liquid waste in Tokai Vitrification Facility

＊Hirotaka Sumi¹, Hikaru Makigaki¹, Jiro Nakayama¹, Koichi Niitsuma¹, Akira Kodaka¹ (1.Japan Atomic Energy Agency)

11:25 AM - 11:40 AM

[3F08] Numerical Simulation of Falling Behavior of Molten Glass with Nobel Metal Elements in Glass Melter

＊Shunji Homma¹, Ryouta Nakajima¹, Midori Uchiyama², Iku Miyasaka², Hiroaki Fujiwara² (1.Saitama University, 2.IHI)

11:40 AM - 11:55 AM

[3F09] Study on ruthenium volatilization during evaporation and drying of ruthenium nitrosyl nitrate solution

Measurement of ruthenium volatilization by using mass spectrometer

＊Tetsuya Kato¹, Tsuyoshi Usami¹, Takeshi Tsukada¹, Yuki Shibata², Takashi Kodama² (1.CRIEPI, 2.JNFL)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral Presentation

[3F10-15] reprocessing process

Mon. Mar 28, 2016 2:45 PM - 4:25 PM Room F (Lecture Rooms B B201)

Chair: Shimada Takashi (MHI)

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2:45 PM - 3:00 PM

[3F10] Durability of Centrifugal Contactors under Sludge Inclusion Condition

(6)Effect of sludge concentration in feed on the accumulation behavior inside rotor

＊Masayuki Takeuchi¹, Atsushi Sakamoto¹, Yuichi Sano¹, Kazuyuki Ito², Satoshi Sekita², Yukio Sakamoto², Koichi Akutsu² (1.Japan Atomic Energy Agency, 2.NECO Ltd.)

3:00 PM - 3:15 PM

[3F11] Durability of Centrifugal Contactors under Sludge Inclusion Condition

(7)Effect of splay nozzles on cleaning up the accumulated sludge

＊Atsushi Sakamoto¹, Yuichi Sano¹, Masayuki Takeuchi¹, Kazuyuki Ito², Satoshi Sekita², Yukio Sakamoto², Koichi Akutsu² (1.JAEA, 2.NECO Ltd.)

3:15 PM - 3:30 PM

[3F12] Development of U and Pu co-processing process

Available condition of Pu reducing agent(as HAN) in the partitioning section

＊Atsunari Kudo¹, Futoshi Yanagibashi¹, Kazuhito Tada¹, Takahiro Hoshi¹, Ikuo Fujimoto¹, Tomoyuki Ohbu¹ (1.Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[3F13] Development of single-cycle separation process for actinides and fission products using novel extractant, NTAamide

(3)mutual separation of Am and Cm

＊Yuji Sasaki¹, Yasuhiro Tsubata¹, Noriko Shirasu¹, Keisuke Morita¹, Shoma Shimazaki¹ (1.Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[3F14] Measurement of the hydrogen concentration in the vessel off-gas generated radiolytically from Pu storage tanks

＊Takahiro Hoshi¹, Shinichi Nagaoka¹, Astunari Kudo¹, Masayuki Oouchi¹, Hiroyasu Isobe¹, Tomoyuki Ohbu¹, Kazuaki Kurabayashi¹ (1.JAEA)

4:00 PM - 4:15 PM

[3F15] Development of spent salt treatment technology using zeolite

(5)Evaluation of zeolite column performance to capture fission product by kinetic mass transfer model

＊Koichi Uozumi¹, Kenta Inagaki¹, Takayuki Terai² (1.Central Research Institute of Electric Power Industry, 2.Univ. of Tokyo)

Time reserved for Chair （4:15 PM - 4:25 PM）

Sessions

IV. Nuclear Fuel Cycle and Nuclear Materials » 404-3. Fuel Reprocessing

[3F01-06] radionuclide separation and recovery

[3F01] R&D of MA separation processes for P&T system using ADS

(6)Development of MA recovery process with TDdDGA

[3F02] R&D of MA separation processes for P&T system using ADS

(7)Examination of Novel Extractants for MA separation

[3F03] EXAFS analysis of europium in various absorbents

[3F04] Separation and recovery of soft metal ions by Copolymer Gel-Silica Composite with
High TPEN Content for Gel-liquid Extraction Process

[3F05] Radiolysis of adsorbent for the extraction chromatography technology

[3F06] Research on solubility of plutonium silicate in nitric acid solution using lanthanides as surrogates for plutonium

[3F07-09] high-level liquid waste and-or glassification

[3F07] Evaluation of Corrosion in the equipment containing High level radioactive liquid waste in Tokai Vitrification Facility

[3F08] Numerical Simulation of Falling Behavior of Molten Glass with Nobel Metal Elements in Glass Melter

[3F09] Study on ruthenium volatilization during evaporation and drying of ruthenium nitrosyl nitrate solution

Measurement of ruthenium volatilization by using mass spectrometer

[3F10-15] reprocessing process

[3F10] Durability of Centrifugal Contactors under Sludge Inclusion Condition

(6)Effect of sludge concentration in feed on the accumulation behavior inside rotor

[3F11] Durability of Centrifugal Contactors under Sludge Inclusion Condition

(7)Effect of splay nozzles on cleaning up the accumulated sludge

[3F12] Development of U and Pu co-processing process

Available condition of Pu reducing agent(as HAN) in the partitioning section

[3F13] Development of single-cycle separation process for actinides and fission products using novel extractant, NTAamide

(3)mutual separation of Am and Cm

[3F14] Measurement of the hydrogen concentration in the vessel off-gas generated radiolytically from Pu storage tanks

[3F15] Development of spent salt treatment technology using zeolite

(5)Evaluation of zeolite column performance to capture fission product by kinetic mass transfer model

Authentication