Oral Presentation

[3B06-09] MA fuel

Fri. Sep 9, 2016 10:55 AM - 12:00 PM Room B (Kumume City Plaza - Gallery 1)

Chair: Shinji Sasaki (JAEA)

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10:55 AM - 11:10 AM

[3B06] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(4)Outline and main results

*Kosuke Tanaka¹, Takayuki Seki¹, Hiroshi Oka¹, Tetsushi Matsuda², Hiroaki Muta³, Ken Sekioka⁴, Daishiro Tokoro⁴ (1.JAEA, 2.JFCC, 3.Osaka University, 4.IDC)

11:10 AM - 11:25 AM

[3B07] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(5)Analysis of densification process using numerical simulation of sintering

*Tetsushi Matsuda¹, Hiroaki Muta², Kosuke Tanaka³ (1.Japan Fine Ceramics Center, 2.Osaka University, 3.Japan Atomic Energy Agency)

11:25 AM - 11:40 AM

[3B08] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(6)Evaluation of fuel properties for simulated MA containing oxide fuel

*Hiroaki Muta¹, Naoki Kato¹, Kosuke Tanaka², Tetsushi Matsuda³, Yuji Ohishi¹, Ken Kurosaki¹, Shinsuke Yamanaka^1,4 (1.Osaka University, 2.Japan Atomic Energy Agency, 3.Japan Fine Ceramics Center, 4.University of Fukui)

11:40 AM - 11:55 AM

[3B09] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(7)Estimation of fuel properties for large amount of simulated MA containing oxide fuel

*Naoki Kato¹, Hiroaki Muta¹, Kosuke Tanaka², Tetsushi Matsuda³, Yuji Ohishi¹, Ken Kurosaki¹, Shinsuke Yamanaka^1,4 (1.Osaka University, 2.Japan Atomic Energy Agency, 3.Japan Fine Ceramics Center, 4.University of Fukui)

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

Oral Presentation

[3B10-12] Molten fuel, FP behavior

Fri. Sep 9, 2016 2:45 PM - 3:35 PM Room B (Kumume City Plaza - Gallery 1)

Chair: Kosuke Tanaka (JAEA)

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2:45 PM - 3:00 PM

[3B10] Leaching tests of TMI-2 debri samples and LWR spent fuels

Release behavior of nuclides under pure-water, boric acid water, and sea water (Part 1)

*Takeshi Sonoda¹, Kenta Inagaki¹, Takanari Ogata¹, Daniel Serrano-Purroy², Jean-Paul Glatz², Vincenzo Rondinella² (1.CRIEPI, 2.ITU)

3:00 PM - 3:15 PM

[3B11] Synthesis of CeO₂ based simulated fuel containing CsI to evaluate the release behavior of Cs and I

*Yuki Takamatsu¹, Ken Kurosaki^1,2, Hiroto Ishii¹, Masahiko Osaka³, Kunihisa Nakajima³, Shuhei Miwa³, Fidelma Giulia Di Lemma³, Yuji Ohishi¹, Hiroaki Muta¹, Shinsuke Yamanaka^1,4 (1.Osaka Univ., 2.JST PREST, 3.Japan Atomic Energy Agency, 4.Univ. of Fukui)

3:15 PM - 3:30 PM

[3B12] Behavior characterization of volatile fission products in meltdown nuclear fuels by a method in consideration of surface and interface effects

(4)Effect of solid surface morphology on melting behavior of CsI

*Hiroto Ishii¹, Ken Kurosaki^1,2, Yukihiro Murakami³, Yuji Ohishi¹, Hiroaki Muta¹, Masayoshi Uno³, Shinsuke Yamanaka^1,3 (1.Osaka Univ., 2.JST PRESTO, 3.Univ. of Fukui)

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

Oral Presentation

[3B13-17] Liquid fuel, MOX fuel

Fri. Sep 9, 2016 3:35 PM - 5:00 PM Room B (Kumume City Plaza - Gallery 1)

Chair: Hiroaki Muta (Osaka Univ.)

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3:35 PM - 3:50 PM

[3B13] Game Changing Potential of Liquid Fuel in Nuclear Industry

*Moto yasu Kinoshita^1,2, Fumihiro Chiba², Takashi Watanabe^2,3, Tsuyoshi Iwashita⁴, Kazuro Furukawa⁵, Masaaki Furukawa² (1.Univ. of Tokyo, 2.TTS inc, 3.NIFS, 4.ES Technology, 5.KEK)

3:50 PM - 4:05 PM

[3B14] Realization of Liquid Nuclear Fuel in Halden Reactor; Irradiation Rig Performance

*Takashi Watanabe¹, Motoyasu Kinoshita^1,2, Fumihiro Chiba¹, Tsuyoshi Iwashita³, Kazuro Furukawa^1,4, Masaaki Furukawa¹, Hartmann Christian⁵, Karlsen Jon-Martin⁵, Beere William⁵, Hansen Jorn-Harald⁵ (1.Thorium Tech Solution inc., 2.U.Tokyo, 3.ESTEX, 4.KEK, 5.IFE)

4:05 PM - 4:20 PM

[3B15] Effect of atmosphere on sintering behavior of (U,Ce)O₂

*Shinya Nakamichi¹, Shun Hirooka¹, Masato Kato¹, Takeo Sunaoshi², Andrew Nelson³, Kenneth McClellan³ (1.Japan Atomic Energy Agency, 2.Inspection Development Company Ltd, 3.Los Alamos National Laboratory)

4:20 PM - 4:35 PM

[3B16] Oxygen potential representation of (U,Pu)O₂

*Masato Kato¹, Masashi Watanabe¹, Hiroki Kato¹, Masahiko Machida¹ (1.Japan Atomic Energy Agency)

4:35 PM - 4:50 PM

[3B17] Restructuring behavior of annular irradiated fuel

*Shinji Sasaki¹, Misaki Isozaki², Akihiro Ishimi¹, Koji Maeda³ (1.Fuels Monitoring Section, Fukushima Fuels and Materials Department, Oarai R&D Center, JAEA , 2.Alfa-Gamma Section, Fukushima Fuels and Materials Department, Oarai R&D Center, JAEA , 3.Materials Monitoring Section, Fukushima Fuels and Materials Department, Oarai R&D Center, JAEA )

Time reserved for Chair （4:50 PM - 5:00 PM）

Sessions

IV. Nuclear Fuel Cycle and Nuclear Materials » 401-2 Nuclear Fuel and the Irradiation Behavior

[3B06-09] MA fuel

[3B06] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(4)Outline and main results

[3B07] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(5)Analysis of densification process using numerical simulation of sintering

[3B08] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(6)Evaluation of fuel properties for simulated MA containing oxide fuel

[3B09] Study on the physical properties of non-stoichiometric oxide fuels with high minor actinide contents

(7)Estimation of fuel properties for large amount of simulated MA containing oxide fuel

[3B10-12] Molten fuel, FP behavior

[3B10] Leaching tests of TMI-2 debri samples and LWR spent fuels

Release behavior of nuclides under pure-water, boric acid water, and sea water (Part 1)

[3B11] Synthesis of CeO₂ based simulated fuel containing CsI to evaluate the release behavior of Cs and I

[3B12] Behavior characterization of volatile fission products in meltdown nuclear fuels by a method in consideration of surface and interface effects

(4)Effect of solid surface morphology on melting behavior of CsI

[3B13-17] Liquid fuel, MOX fuel

[3B13] Game Changing Potential of Liquid Fuel in Nuclear Industry

[3B14] Realization of Liquid Nuclear Fuel in Halden Reactor; Irradiation Rig Performance

[3B15] Effect of atmosphere on sintering behavior of (U,Ce)O₂

[3B16] Oxygen potential representation of (U,Pu)O₂

[3B17] Restructuring behavior of annular irradiated fuel

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