Oral presentation

[1I09-13] Fuel Production/Storage Technology

Wed. Mar 16, 2022 2:45 PM - 4:05 PM Room I

Chair: Fumihiro Nakamori (CRIEPI)

2:45 PM - 3:00 PM

[1I09] Technological development of the particle size adjustment of recycle powder

(6)Study on test facility for dry recycling of MOX powder and development of sintered density control technology

*Kazuya Yamamoto¹, Tomoomi Segawa¹, Takayoshi Makino¹, Koichi Kawaguchi¹, Hidetoshi iso¹, Katsunori Ishii¹ (1. JAEA)

3:00 PM - 3:15 PM

[1I10] Technological development of the particle size adjustment of recycle powder

(7)Study on sintering density prediction method for the pellet with dry recycled powder

*Koichi Kawaguchi¹, Kazuya Yamamoto¹, Takayoshi Makino¹, Hidetoshi Iso¹, Tomoomi Segawa, Katsunori Ishii (1. JAEA)

3:15 PM - 3:30 PM

[1I11] Sintering behavior of recycled MOX powder

*Shinya Nakamichi¹, Takeo Sunaoshi², Hiroki Uno², Tadahisa Yamada², Kazuyuki Okumura¹ (1. Japan Atomic Energy Agency, 2. Inspection Development)

3:30 PM - 3:45 PM

[1I12] Development of MOX weighting and blending equipment on Plutonium Fuel Production Facility

*Kohei Kawasaki¹, Kenta Shinada¹, Naritoshi Okamoto¹, Takanori Ono¹, Kimikazu Shibanuma¹, Kenta Goto¹ (1. Japan Atomic Energy Agency)

3:45 PM - 4:00 PM

[1I13] Stabilization of post-experiment nuclear materials containing resins by oxidation heat treatment

*Takumi Sato¹, Kazuki Morishita¹, Haruyoshi Otobe¹, Tadatsune Fujishima¹, Tomoyuki Nakano¹ (1. JAEA)

Time reserved for Chair （4:00 PM - 4:05 PM）

Oral presentation

[1I14-16] Irradiation Behaviour of LWR Fuel / Accident Tolerant Fuel

Wed. Mar 16, 2022 4:05 PM - 4:55 PM Room I

Chair: Mutsumi Hirai (TEPCO HD)

4:05 PM - 4:20 PM

[1I14] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(3)TEM-EDS analysis of MDA after neutron or Zr ion irradiation

*Takashi Sawabe¹, Fumihiro Nakamori¹, Takeshi Sonoda¹ (1. CRIEPI)

4:20 PM - 4:35 PM

[1I15] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(4)Atom probe analysis of MDA after neutron or Zr ion irradiation

*Fumihiro Nakamori¹, Takashi Sawabe¹, Takeshi Sonoda¹ (1. CRIEPI)

4:35 PM - 4:50 PM

[1I16] BWR fuel assembly "KAMADO-BWR" using SiC block with high accident resistance

Preliminary study of basic concept, temperature distribution and critical heat flux

*Tetsuo Matsumura¹, Takanori Kameyama¹ (1. Tokai University)

Time reserved for Chair （4:50 PM - 4:55 PM）

Oral presentation

[1I17-18] Nitride Fuel/HTGR Fuel

Wed. Mar 16, 2022 4:55 PM - 5:30 PM Room I

Chair: Mutsumi Hirai (TEPCO HD)

4:55 PM - 5:10 PM

[1I17] Application of Laser Spot Heating Method to Measurement of Nitrides Melting Temperature

*Tohma Iwasa¹, Masahide Takano¹ (1. JAEA)

5:10 PM - 5:25 PM

[1I18] Study on SiC compact oxidation under HTGR air ingress accident

(1)SiC oxidation experiment

*Yosuke Nishimura¹ (1. University of Tokyo )

Time reserved for Chair （5:25 PM - 5:30 PM）

Oral presentation

[2I01-07] Fast Reactor Fuel Development

Thu. Mar 17, 2022 10:00 AM - 12:00 PM Room I

Chair: Masato Kato (JAEA)

10:00 AM - 10:15 AM

[2I01] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(1)Advanced technology of microwave heating denitration method

*Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Hayahisa suchida², Kota Fujiwara², Akiko Kaneko², Yutaka Abe² (1. JAEA, 2. Univ. of Tsukuba)

10:15 AM - 10:30 AM

[2I02] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(2)Die wall lubrication technology with using tumbling granular

*Kiyoto Takato¹, Masahiro Nishina¹, Tomoomi Segawa¹, Ryota Tsuchimochi¹, Kohei Hayashizaki¹, Takayoshi Makino¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Kazuyuki Okumura¹ (1. JAEA)

10:30 AM - 10:45 AM

[2I03] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(3)Sintering and O/M ratio adjustment technology and gas flow analysis

*Masahiro Nishina¹, Kiyoto Takato¹, Nakamichi Shinya¹, Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Takayoshi Makino¹, Kazuyuki Okumura¹ (1. JAEA)

10:45 AM - 11:00 AM

[2I04] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(4)Development of visual inspection technology of pellets using machine learning

*Shun Hirooka¹, Yuta Horii¹, Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Takayoshi Makino¹, Kazuyuki Okumura¹ (1. JAEA)

11:00 AM - 11:15 AM

[2I05] The measurement of thermal conductivity of MOX including simulated FPs and impurities

*Yuta Horii¹, Shun Hirooka¹, Masato Kato¹, Hiroki Uno², Masahiro Ogasawara², Tetsuya Tamura², Tadahisa Yamada², Kazuyuki Okumura¹ (1. JAEA, 2. Inspection Development)

11:15 AM - 11:30 AM

[2I06] Suppression of hydrogen permeation from stainless steel cladding tubes loaded with zirconium hydride

*Kenji Konashi¹, Satoru Matsuo¹, Atsushi Ohuchi², Toru Higuchi², Mutsumi Hirai², Hiroyuki Kazama³ (1. Tohoku Univ., 2. NFD, 3. JAEA)

11:30 AM - 11:45 AM

[2I07] Feasibitlity of Helium-bond Particulate Metal Fuel

*Takanari Ogata¹ (1. CRIEPI)

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

Sessions

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

[1I09-13] Fuel Production/Storage Technology

[1I09] Technological development of the particle size adjustment of recycle powder

(6)Study on test facility for dry recycling of MOX powder and development of sintered density control technology

[1I10] Technological development of the particle size adjustment of recycle powder

(7)Study on sintering density prediction method for the pellet with dry recycled powder

[1I11] Sintering behavior of recycled MOX powder

[1I12] Development of MOX weighting and blending equipment on Plutonium Fuel Production Facility

[1I13] Stabilization of post-experiment nuclear materials containing resins by oxidation heat treatment

[1I14-16] Irradiation Behaviour of LWR Fuel / Accident Tolerant Fuel

[1I14] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(3)TEM-EDS analysis of MDA after neutron or Zr ion irradiation

[1I15] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(4)Atom probe analysis of MDA after neutron or Zr ion irradiation

[1I16] BWR fuel assembly "KAMADO-BWR" using SiC block with high accident resistance

Preliminary study of basic concept, temperature distribution and critical heat flux

[1I17-18] Nitride Fuel/HTGR Fuel

[1I17] Application of Laser Spot Heating Method to Measurement of Nitrides Melting Temperature

[1I18] Study on SiC compact oxidation under HTGR air ingress accident

(1)SiC oxidation experiment

[2I01-07] Fast Reactor Fuel Development

[2I01] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(1)Advanced technology of microwave heating denitration method

[2I02] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(2)Die wall lubrication technology with using tumbling granular

[2I03] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(3)Sintering and O/M ratio adjustment technology and gas flow analysis

[2I04] Development of simplified pelletizing process for fast reactor MOX fuels and demonstration experiment

(4)Development of visual inspection technology of pellets using machine learning

[2I05] The measurement of thermal conductivity of MOX including simulated FPs and impurities

[2I06] Suppression of hydrogen permeation from stainless steel cladding tubes loaded with zirconium hydride

[2I07] Feasibitlity of Helium-bond Particulate Metal Fuel

Authentication