Oral presentation

[2B09-11] Pyroprocessing

Thu. Sep 7, 2023 2:45 PM - 3:35 PM Room B (IB Bildg.1F IB014)

Chair:Yuma Sekiguchi(CRIEPI)

2:45 PM - 3:00 PM

[2B09] Applicability of conductive oxides to oxygen-evolving inert anode in LiCl-Li₂O melts

*Yoshiharu Sakamura¹, Tsuyoshi Murakami¹, Masatoshi Iizuka¹, Hirohide Kofuji² (1. CRIEPI, 2. JAEA)

3:00 PM - 3:15 PM

[2B10] Development of interface technology for domestic introduction of metal fuel cycle

(1)Reduction characteristics of metal oxides based on polarization curve measurement in molten salt electroreduction method

*Kaname SAGA¹, Daisuke WATANABE², Hirotaka NAKAHARA² (1. Hitachi, Ltd., 2. HGNE)

3:15 PM - 3:30 PM

[2B11] High-temperature reaction of Gd_0.25Zr_0.75N with Pd (2) Temperature dependence of the reaction product composition

*Ria Mishima¹, Takumi Sato¹, Hirokazu Hayashi¹ (1. JAEA)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral presentation

[2B12-14] Aqueous Separation

Thu. Sep 7, 2023 3:35 PM - 4:25 PM Room B (IB Bildg.1F IB014)

Chair:Yoshiharu Sakamura(CRIEPI)

3:35 PM - 3:50 PM

[2B12] Mutual Separation of Lanthanides by Stimuli-Responsive Zwitterionic Polymer Brushes

*Tommy Suhartono Wijaya Tan¹, Naokazu Idota¹, Takehiko Tsukahara¹ (1. Tokyo Tech)

3:50 PM - 4:05 PM

[2B13] Extraction behaviors of minor actinides and rare earth elements with four NTA amide extractants

*Hideya Suzuki¹, Satoshi Nakamura¹, Tatsuya Emori¹, Tatsuya Kurosawa¹, Mitsunobu Shibata¹, Tomohiro Kawasaki¹, Yasutoshi Ban¹ (1. Japan Atomic Energy Agency)

4:05 PM - 4:20 PM

[2B14] Extraction Properties of Acidic Diamide-type Extractant toward Minor Actinides and Rare Earth Elements

*Satoshi Nakamura¹, Hideya Suzuki¹, Sho Ishii¹, Tatsuya Emori¹, Tatsuya Kurosawa¹, Mitsunobu Shibata¹, Kojiro Shimojo¹, Yasutoshi Ban¹ (1. JAEA)

Time reserved for Chair （4:20 PM - 4:25 PM）

Oral presentation

[2B15-17] Boiling and Drying Accident

Thu. Sep 7, 2023 4:25 PM - 5:15 PM Room B (IB Bildg.1F IB014)

Chair:Hideya Suzuki(JAEA)

4:25 PM - 4:40 PM

[2B15] Enhancement of Analysis Method for Important Phenomena of Severe Accident at Reprocessing Plant

(D-9) Current Status and Future Perspective of FATE Enhancement Plan Based on the PIRT

*Daisuke Fujiwara¹, Hisayuki Kyo¹, Hiroshi Shirai¹, Takashi Kodama², Yoshikazu Tamauchi², Naoya Sato² (1. TEPSYS, 2. Japan Nuclear Fuel Limited)

4:40 PM - 4:55 PM

[2B16] Enhancement of Analysis Method for Important Phenomena of Severe Accident at Reprocessing Plant

(D-10) Validation of Evaluation Models for Important Phenomena in HALW Boiling and Drying Accident

*Hisayuki Kyo¹, Daisuke Fujiwara¹, Hiroshi Shirai¹, Takashi Kodama², Yoshikazu Tamauchi², Naoya Sato² (1. TEPCO SYSTEMS CORPORATION, 2. Japan Nuclear Fuel Limited)

4:55 PM - 5:10 PM

[2B17] Study on applicability of zeolite for mitigation of RuO₄ release

(2) Estimation of gas removal feature of X-type zeolite with small-scale column equipment

*Yuma Sekiguchi¹, Tetsuya Kato¹, Tsuyoshi Usami¹ (1. CRIEPI)

Time reserved for Chair （5:10 PM - 5:15 PM）

Oral presentation

[2B18-21] MOX Reprocessing and Cycle Evaluation

Thu. Sep 7, 2023 5:15 PM - 6:25 PM Room B (IB Bildg.1F IB014)

Chair:Daisuke Fujiwara(TEPSYS)

5:15 PM - 5:30 PM

[2B18] Research program of technical base for spent MOX fuels reprocessing

(1) Overview and MOX fuel fabrication

*Masayuki Takeuchi¹, Kazunori Nomura¹, Takahiro Ishio², Yoshinobu Niitsu² (1. Japan Atomic Energy Agency, 2. Japan Nuclear fuel Ltd.)

5:30 PM - 5:45 PM

[2B19] Research program of technical base for spent MOX fuels reprocessing

(2)Nitric acid dissolution test of non-irradiated MOX pellets

*Shuya Kimura¹, Haruka Aihara¹, Masaumi Nakahara¹, Kimihiko Yano¹, Shinichi Kitawaki¹, Yuichi Sano¹, Masayuki Takeuchi¹ (1. JAEA)

5:45 PM - 6:00 PM

[2B20] Implementation of a calculation model to simulate re-enrichment of recovered uranium in nuclear fuel cycle simulator NMB4.0

*Takumi Abe¹, Kenji Nishihara¹ (1. JAEA)

6:00 PM - 6:15 PM

[2B21] Evaluation of diffused and retained actinide inventory in SiC layer in HTGR spent fuel

*Koei Sasaki¹, Yuji Fukaya¹, Yukio Tachibana¹, Kazuhiro Sawa² (1. JAEA, 2. Hokkaido Univ.)

Time reserved for Chair （6:15 PM - 6:25 PM）

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 504-3 Fuel Reprocessing

[2B09-11] Pyroprocessing

[2B09] Applicability of conductive oxides to oxygen-evolving inert anode in LiCl-Li₂O melts

[2B10] Development of interface technology for domestic introduction of metal fuel cycle

(1)Reduction characteristics of metal oxides based on polarization curve measurement in molten salt electroreduction method

[2B11] High-temperature reaction of Gd_0.25Zr_0.75N with Pd (2) Temperature dependence of the reaction product composition

[2B12-14] Aqueous Separation

[2B12] Mutual Separation of Lanthanides by Stimuli-Responsive Zwitterionic Polymer Brushes

[2B13] Extraction behaviors of minor actinides and rare earth elements with four NTA amide extractants

[2B14] Extraction Properties of Acidic Diamide-type Extractant toward Minor Actinides and Rare Earth Elements

[2B15-17] Boiling and Drying Accident

[2B15] Enhancement of Analysis Method for Important Phenomena of Severe Accident at Reprocessing Plant

(D-9) Current Status and Future Perspective of FATE Enhancement Plan Based on the PIRT

[2B16] Enhancement of Analysis Method for Important Phenomena of Severe Accident at Reprocessing Plant

(D-10) Validation of Evaluation Models for Important Phenomena in HALW Boiling and Drying Accident

[2B17] Study on applicability of zeolite for mitigation of RuO₄ release

(2) Estimation of gas removal feature of X-type zeolite with small-scale column equipment

[2B18-21] MOX Reprocessing and Cycle Evaluation

[2B18] Research program of technical base for spent MOX fuels reprocessing

(1) Overview and MOX fuel fabrication

[2B19] Research program of technical base for spent MOX fuels reprocessing

(2)Nitric acid dissolution test of non-irradiated MOX pellets

[2B20] Implementation of a calculation model to simulate re-enrichment of recovered uranium in nuclear fuel cycle simulator NMB4.0

[2B21] Evaluation of diffused and retained actinide inventory in SiC layer in HTGR spent fuel

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