Oral presentation

[3K01-06] Fast Reactor Recycling

Fri. Mar 19, 2021 10:15 AM - 12:00 PM Room K (Zoom room 11)

Chair: Ken Kurosaki (Kyoto Univ.)

10:15 AM - 10:30 AM

[3K01] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(1)Research program

*Masato Kato¹, Masami Uno², Tatsumi Arima³ (1. JAEA, 2. Fukui Univ., 3. Kyushu Univ.)

10:30 AM - 10:45 AM

[3K02] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(2)Sintering test of MOX with simulated FP(Nd₂O₃,Sm₂O₃)

*Yuta Horii¹, Masato Kato¹, Shun Hirooka¹, Hiroki Uno², Tetsuya Tamura², Takeo Sunaoshi² (1. JAEA, 2. Inspection Development)

10:45 AM - 11:00 AM

[3K03] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(3)The thermal conductivity of 10% Am-bearing MOX fuels

*Keisuke Yokoyama¹, Masashi Watanabe¹, Masato Kato¹, daishiro tokoro², Masatoshi sugimoto² (1. JAEA, 2. Inspection Development)

11:00 AM - 11:15 AM

[3K04] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(4)Development of measurement technology for thermal conductivity in the radial direction of pellet using transient plane heat source method

*Haruka Okazaki¹, Takashi Onitsuka¹, Masayoshi Uno¹ (1. Univ. of Fukui)

11:15 AM - 11:30 AM

[3K05] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(5)Development of measurement technique for local melting point of fuel pellet with laser heating

*Tatsumi Arima¹, Masato Kato² (1. Kyushu Univ., 2. JAEA)

11:30 AM - 11:45 AM

[3K06] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(6)ARES-MOX Transient Program for Irradiated MOX fuels in TREAT

*Takayuki Ozawa¹, Shun Hirooka¹, Masato Kato¹, Trevor J. Smuin², Colby B. Jensen², Nicolas E. Woolstenhulme², Daniel M. Wachs² (1. JAEA, 2. INL)

Time reserved for Chair （11:45 AM - 12:00 PM）

Oral presentation

[3K07-10] Development for Fast Reactor Fuel

Fri. Mar 19, 2021 2:45 PM - 3:55 PM Room K (Zoom room 11)

Chair: Tatsumi Arima (Kyushu Univ.)

2:45 PM - 3:00 PM

[3K07] X-Ray Computed Tomography Image Analysis of an Irradiated Joyo Fuel Assembly: Visualization of the Structural Changes in the Irradiated Fuels

*Tien-Hsiu Tsai¹, Shinji Sasaki¹, Kozo Katsuyama¹, Koji Maeda¹ (1. JAEA)

3:00 PM - 3:15 PM

[3K08] Granulation characteristics confirmation test of additive-free dry granulation technology for fast reactor fuel fabrication

*Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Masahiro Nishina¹, Takayoshi Makino¹, Yuri Natori², Norihiro Ikemoto², Kazuo Yonehara², Katsuyoshi Tatenuma² (1. JAEA, 2. KAKEN)

3:15 PM - 3:30 PM

[3K09] Development of Light Water Cooled Fast Reactor

(5)Sintering test of MOX fuel pellets containing high Pu -1-

*kyoichi morimoto¹, Masashi Watanabe¹, Masato Kato¹, Tetsushi Hino² (1. JAEA, 2. HGNE)

3:30 PM - 3:45 PM

[3K10] Development of metal nanoparticle dispersion technique for liquid sodium

Experimental study of the requisites for dispersing technique

*Keiichi Nagai¹, Masahiko Ohtaka¹, Chikai Tei¹ (1. JAEA)

Time reserved for Chair （3:45 PM - 3:55 PM）

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[3K01-06] Fast Reactor Recycling

[3K01] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(1)Research program

[3K02] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(2)Sintering test of MOX with simulated FP(Nd₂O₃,Sm₂O₃)

[3K03] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(3)The thermal conductivity of 10% Am-bearing MOX fuels

[3K04] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(4)Development of measurement technology for thermal conductivity in the radial direction of pellet using transient plane heat source method

[3K05] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(5)Development of measurement technique for local melting point of fuel pellet with laser heating

[3K06] Demonstration research on fast reactor recycling using low decontaminated MA-bearing MOX fuels

(6)ARES-MOX Transient Program for Irradiated MOX fuels in TREAT

[3K07-10] Development for Fast Reactor Fuel

[3K07] X-Ray Computed Tomography Image Analysis of an Irradiated Joyo Fuel Assembly: Visualization of the Structural Changes in the Irradiated Fuels

[3K08] Granulation characteristics confirmation test of additive-free dry granulation technology for fast reactor fuel fabrication

[3K09] Development of Light Water Cooled Fast Reactor

(5)Sintering test of MOX fuel pellets containing high Pu -1-

[3K10] Development of metal nanoparticle dispersion technique for liquid sodium

Experimental study of the requisites for dispersing technique

Authentication

Sessions

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[3K01-06] Fast Reactor Recycling

(1)Research program

(2)Sintering test of MOX with simulated FP(Nd2O3,Sm2O3)

(3)The thermal conductivity of 10% Am-bearing MOX fuels

(4)Development of measurement technology for thermal conductivity in the radial direction of pellet using transient plane heat source method

(5)Development of measurement technique for local melting point of fuel pellet with laser heating

(6)ARES-MOX Transient Program for Irradiated MOX fuels in TREAT

[3K07-10] Development for Fast Reactor Fuel

(5)Sintering test of MOX fuel pellets containing high Pu -1-

Experimental study of the requisites for dispersing technique

Authentication

(2)Sintering test of MOX with simulated FP(Nd₂O₃,Sm₂O₃)