Oral presentation

[1D01-06] Fuel Debris

Wed. Sep 5, 2018 10:15 AM - 11:55 AM Room D (A32 -A Building)

Chair:Tatsumi Arima(Kyushu Univ.)

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10:15 AM - 10:30 AM

[1D01] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(9)Outline of the Project and Results of Fuel Debris Research

*Msayoshi uno¹, Yoshinari Anoda¹, Osamu Kuwazuru², Yuuji Arita¹, Akihiro Ishimi³, Tatsumi Arima⁴ (1. Research Institute of Nuclear Engineering, University of Fukui, 2. Graduate school of Engineering, University of Fukui, 3. Japan Atomic Energy Agency, 4. Kyushu University)

10:30 AM - 10:45 AM

[1D02] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(10)Properties of Frozen Body of Melted Debris Containing UO₂

*Takashi Onitsuka¹, Kozo Katsuyama², Akihiro Ishimi², Masayoshi Uno¹ (1. Univ. of Fukui, 2. JAEA)

10:45 AM - 11:00 AM

[1D03] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(11) Microscopic material properties and macroscopic compression strength of simulated nuclear fuel debris

*Aruto Kawakami¹, Masaki Teranishi¹, Osamu Kuwazuru¹ (1. Fukui Univ)

11:00 AM - 11:15 AM

[1D04] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(12) Formation and dissolution behavior of SrZrO₃

*Taishi Inoue¹, Yuji Arita¹, Toru Fujita¹ (1. University of Fukui)

11:15 AM - 11:30 AM

[1D05] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(13)Melting behaviors of CeO2-ZrO2 and UO2-ZrO2

*Tohma Iwasa¹, Tatsumi Arima¹ (1. Kyushu University)

11:30 AM - 11:45 AM

[1D06] Chemical states of plutonium and gadolinium in fuel debris

*Shiho Watanabe¹, Hiroto Ishii¹, Yuji Ohishi¹, Hiroaki Muta¹, Ken Kurosaki^1,2,3 (1. Osaka University, 2. Research Institute of Nuclear Engineering, University of Fukui, 3. JST PRESTO)

Time reserved for Chair （11:45 AM - 11:55 AM）

Oral presentation

[1D07-09] Fundamental Properties

Wed. Sep 5, 2018 2:45 PM - 3:35 PM Room D (A32 -A Building)

Chair:Masahide Takano(JAEA)

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2:45 PM - 3:00 PM

[1D07] Thermal and mechanical properties of Fe₂Zr

*Daisuke Okada¹, Hiroto Ishii¹, Yuji Ohishi¹, Hiroaki Muta¹, Ken Kurosaki^1,2,3 (1. Osaka University, 2. Research Institute of Nuclear Engineering, University of Fukui, 3. JST PRESTO)

3:00 PM - 3:15 PM

[1D08] Hydrogen distribuiton in irradiated zirconium alloys by means of atom probe tomography

*Takashi Sawabe¹, Takeshi Sonoda¹ (1. CRIEPI)

3:15 PM - 3:30 PM

[1D09] Thermal properties evaluation of fluorite structure oxides

*Masato Kato¹, Taku Matsumoto¹, Hiroki Nakamura¹, Masahiko Machida¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[1D10-12] Fuel Behavior

Wed. Sep 5, 2018 3:35 PM - 4:25 PM Room D (A32 -A Building)

Chair:Masayoshi Uno(Univ. of Fukui)

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3:35 PM - 3:50 PM

[1D10] Evaluation of fuel behaviors by using science-based Integrated models for MOX properties

(1)Evaluation of O/M redistribution

*Shun Hirooka¹, Masato Kato¹, Masashi Watanabe¹ (1. Japan Atomic Energy Agency)

3:50 PM - 4:05 PM

[1D11] Evaluation of fuel behaviors by using science-based Integrated models for MOX properties

(2)Evaluation of Pu and Am redistribution

*Miho Kamei¹, Masayuki Naganuma¹, Yoshihisa Ikusawa¹, Koji Maeda¹, Shinji Sasaki¹, Ozawa Takayuki¹, Shun Hirooka¹ (1. JAEA)

4:05 PM - 4:20 PM

[1D12] Development of Fuel Performance Code FEMAXI-8

Model Improvements for Light Water Reactor Fuel Analysis and Systematic Validation

*Yutaka Udagawa¹, Masaki Amaya¹ (1. Japan Atomic Energy Agency)

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

Oral presentation

[1D13-18] Nitride Fuel

Wed. Sep 5, 2018 4:25 PM - 6:00 PM Room D (A32 -A Building)

Chair:Masato Kato(JAEA)

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4:25 PM - 4:40 PM

[1D13] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

Lattice and Bulk Expansion of Nitride Fuel Pellet Induced by Self-irradiation Damage

*Masahide Takano¹, Seiya Takaki¹ (1. JAEA)

4:40 PM - 4:55 PM

[1D14] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(4) Correlation of Milling Condition and Sintered Density of Nitride Fuel Surrogate Material

*Seiya Takaki¹, Makoto Harada¹, Masahide Takano¹ (1. Japan Atomic Energy Agency)

4:55 PM - 5:10 PM

[1D15] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(5)Chemical Compatibility between Cladding and Fuel Surrogate Materials

*Harada Makoto¹, Seiya Takaki¹, Masahide Takano¹ (1. JAEA)

5:10 PM - 5:25 PM

[1D16] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(6)Melting Point Measurement of Nitride: A Laser Heating Application

*Tatsumi Arima¹, Masahide Takano², Seiiya Takaki² (1. Kyushu univ., 2. Japan atomic energy agency)

5:25 PM - 5:40 PM

[1D17] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(7) Shearing experiments of simulated fuel pins containing (Dy,Zr)N pellets

*Takumi Sato¹, Hirokazu Hayashi¹ (1. Japan Atomic Energy Agency)

5:40 PM - 5:55 PM

[1D18] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(8) Reductive extraction of Zr and Ce in liquid Cd

*TSUYOSHI MURAKAMI¹, Masatoshi Iizuka¹, Hirokazu Hayashi² (1. Central Research Institute of Electric Power Industry, 2. Japan Atomic Energy Agency)

Time reserved for Chair （5:55 PM - 6:00 PM）

Oral presentation

[2D01-04] Accident-tolerant Fuel 1

Thu. Sep 6, 2018 9:30 AM - 10:35 AM Room D (A32 -A Building)

Chair:Kunihiro Itoh(NDC)

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9:30 AM - 9:45 AM

[2D01] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(1) Overview of project

*Shinichiro Yamashita¹, Seiichi Watanabe², Nozomu Murakami³, Hisaki Sato⁴, Takao Kondo⁵, Takashi Nozawa⁶, Kan Sakamoto⁷, Kazuyuki Kusagaya⁸, Shigeharu Ukai⁹, Akihiko Kimura¹⁰ (1. JAEA, 2. MNF, 3. MHI, 4. Toshiba ESS, 5. Hitachi-GE, 6. QST, 7. NFD, 8. GNF-J, 9. Hokkaido Univ., 10. Kyoto Univ.)

9:45 AM - 10:00 AM

[2D02] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(2) FeCrAl-ODS steels for BWR fuel claddings

*Kan SAKAMOTO¹, Shigeharu Ukai², Akihiko Kimura³, Akifumi Yamaji⁴, Kazuyuki Kusagaya⁵, Takao Kondo⁶, Shinichiro Yamashita⁷, Fukahori Tokio⁷ (1. NFD, 2. Hokkaido Univ., 3. Kyoto Univ., 4. Waseda Univ., 5. GNF-J, 6. Hitachi-GE, 7. JAEA)

10:00 AM - 10:15 AM

[2D03] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(3) SiC for BWR

*Hisaki Sato¹, Kazuo Kakiuchi¹, Ryo Ishibashi², Tomohiko Ikegawa², Takao Kondo², Shinichiro Yamashita³, Tokio Fukahori³ (1. Toshiba ESS Corporation, Nuclear Safety System Design & Engineering Department, 2. Hitachi GE, 3. JAEA)

10:15 AM - 10:30 AM

[2D04] R&D for introducing advanced fuels contributing to safety improvement of current LWRs

(4) SiC composite material for PWR

*seiichi watanabe¹, Daiki Sato¹, Kenichiro Furumoto¹, Nozomu Murakami³, Shinichiro Yamashita², Tokio Fukahori² (1. MNF, 2. JAEA, 3. MHI)

Time reserved for Chair （10:30 AM - 10:35 AM）

Oral presentation

[2D05-09] Accident-tolerant Fuel 2

Thu. Sep 6, 2018 10:35 AM - 12:00 PM Room D (A32 -A Building)

Chair:Kan Sakamoto(NFD)

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10:35 AM - 10:50 AM

[2D05] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(5) Evaluation of influence on core neutronics characteristics and fuel behavior

*Nozomu Murakami¹, Kazuki Kirimura¹, Kazuya Yamaji¹, Daisuke Sato¹, Seiichi Watanabe², Daiki Sato², Kenichiro Furumoto², Shinichiro Yamashita³, Tokio Fukahori³ (1. MHI, 2. MNF, 3. JAEA)

10:50 AM - 11:05 AM

[2D06] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(6) Mechanical property test

*Kenichiro Furumoto¹, Daiki Sato¹, Seiichi Watanabe¹, Shinichiro Yamashita², Tokio Fukahori² (1. MNF, 2. JAEA)

11:05 AM - 11:20 AM

[2D07] The feasibility study on SiC composite fuel cladding for the Accident Tolerant Fuel to the existing PWR plants

(7) LOCA simulated test

*Daiki Sato¹, Seiichi Watabe¹, Daisuke Komiyama¹, Kenichiro Furumoto¹, Michiaki Okamoto², Masaaki Yamato², Yamashita Shinichiro³, Tokio Fukahori³ (1. MNF, 2. MHI, 3. JAEA)

11:20 AM - 11:35 AM

[2D08] R&D for introducing silicon carbide materials to safety improvement of BWRs core

(3) Plant transient analysis with SiC clad fuel for RIA accident

*Hideki Horie¹, Yutaka Takeuchi¹, Kazuo Kakiuchi¹, Hisaki Sato¹, Noriko Shirasu², Hiroaki Saito², Shinichiro Yamashita², Tokio Fukahori² (1. Toshiba Energy Systems & Solutions Corporation, 2. Japan Atomic Energy Agency)

11:35 AM - 11:50 AM

[2D09] High Temperature Formation Behavior of SiO₂ Oxide Film Formed on Surface of SiC

*Souichirou Yamaguchi¹, Takashi Onithuka², Masayoshi Uno² (1. University of Fukui graduate school of engineering Advanced Interdisciplinary Science and Technology, 2. Research Institute of Nuclear Engineering)

Time reserved for Chair （11:50 AM - 12:00 PM）

Oral presentation

[2D10-17] Accident-tolerant Fuel 3

Thu. Sep 6, 2018 2:45 PM - 4:55 PM Room D (A32 -A Building)

Chair:Ken Kurosaki(Osaka Univ.)

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2:45 PM - 3:00 PM

[2D10] R&D of advanced stainless steels for BWR fuel claddings (3)

(1) Fuel performance during severe accident with accident management

*Tomohiko Ikegawa¹, Ryo Ishibashi¹, Kan Sakamoto², Shinichiro Yamashita³ (1. Hitachi-GE, 2. NFD, 3. JAEA)

3:00 PM - 3:15 PM

[2D11] R&D of advanced stainless steels for BWR fuel claddings (3)

(2) Applicability of MOX fuel core design

*Sho Takano¹, Daisuke Goto¹, Kazuyuki Kusagaya¹, Kan Sakamoto², Shinichiro Yamashita³ (1. GNF-J, 2. NFD, 3. JAEA)

3:15 PM - 3:30 PM

[2D12] R&D of advanced stainless steels for BWR fuel claddings (3)

(3) Mechanical properties of manufactured steels

*Mohammad Aghamiri¹, Shigeharu Ukai¹, Naoko Oono¹, Shigenari Hayashi¹, Takashi Sowa¹, Naoya Sugawara¹, Hiroshi Sakamoto², Yamashita Shinichiro³ (1. Hokkaido Univ., 2. NFD, 3. JAEA)

3:30 PM - 3:45 PM

[2D13] R&D of advanced stainless steels for BWR fuel claddings (3)

(4) Endurance for fuel failure under normal operation condition

*Yusuke Miura¹, Kan Sakamoto¹, Shinichiro Yamashita², Tokio Fukahori² (1. NFD, 2. JAEA)

3:45 PM - 4:00 PM

[2D14] R&D of advanced stainless steels for BWR fuel claddings (3)

(5) Welding and inspection

*Akihiko Kimura¹, Yuuki Yanmasaki¹, Kiyohiro Yabuuchi¹, Kan Sakamoto², Shinnichiro Yamashita³, Kazuyuki Kusagaya⁴ (1. IAE, Kyoto University, 2. NFD, 3. JAEA, 4. GNF-J)

4:00 PM - 4:15 PM

[2D15] R&D of advanced stainless steels for BWR fuel claddings (3)

(6) End-plug joining test applying PRW technique

*Takashi Tanno¹, Yasuhide Yano¹, Tatsuya Tsukada¹, Kan Sakamoto², Shinichiro Yamashita¹ (1. JAEA, 2. NFD)

4:15 PM - 4:30 PM

[2D16] R&D of advanced stainless steels for BWR fuel claddings (3)

(7) Evaluation of irradiation behavior

*Naoyuki Hashimoto¹, Kodai Toyota¹, Yixiang Tang¹, Kan Sakamoto², Shinichiro Yamashita³ (1. Faculty of Engineering, Hokkaido University, 2. Nippon Nuclear Fuel Development Co., 3. Japan Atomic Energy Agency )

4:30 PM - 4:45 PM

[2D17] R&D of advanced stainless steels for BWR fuel claddings (3)

(8) Mechanical properties after neutron irradiation

*Katsuhito Takahahshi¹, Mitsuo Nozue¹, Yusuke Miura¹, Kan Sakamoto¹, Akihiko Kimura², Sigeharu Ukai³, Shin-ichirou Yamashita⁴ (1. NFD, 2. Kyoto Univ., 3. Hokkaido Univ., 4. JAEA)

Time reserved for Chair （4:45 PM - 4:55 PM）

Sessions

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

[1D01-06] Fuel Debris

(9)Outline of the Project and Results of Fuel Debris Research

(10)Properties of Frozen Body of Melted Debris Containing UO2

(11) Microscopic material properties and macroscopic compression strength of simulated nuclear fuel debris

(12) Formation and dissolution behavior of SrZrO3

(13)Melting behaviors of CeO2-ZrO2 and UO2-ZrO2

[1D07-09] Fundamental Properties

[1D10-12] Fuel Behavior

(1)Evaluation of O/M redistribution

(2)Evaluation of Pu and Am redistribution

Model Improvements for Light Water Reactor Fuel Analysis and Systematic Validation

[1D13-18] Nitride Fuel

Lattice and Bulk Expansion of Nitride Fuel Pellet Induced by Self-irradiation Damage

(4) Correlation of Milling Condition and Sintered Density of Nitride Fuel Surrogate Material

(5)Chemical Compatibility between Cladding and Fuel Surrogate Materials

(6)Melting Point Measurement of Nitride: A Laser Heating Application

(7) Shearing experiments of simulated fuel pins containing (Dy,Zr)N pellets

(8) Reductive extraction of Zr and Ce in liquid Cd

[2D01-04] Accident-tolerant Fuel 1

(1) Overview of project

(2) FeCrAl-ODS steels for BWR fuel claddings

(3) SiC for BWR

(4) SiC composite material for PWR

[2D05-09] Accident-tolerant Fuel 2

(5) Evaluation of influence on core neutronics characteristics and fuel behavior

(6) Mechanical property test

(7) LOCA simulated test

(3) Plant transient analysis with SiC clad fuel for RIA accident

[2D10-17] Accident-tolerant Fuel 3

(1) Fuel performance during severe accident with accident management

(2) Applicability of MOX fuel core design

(3) Mechanical properties of manufactured steels

(4) Endurance for fuel failure under normal operation condition

(5) Welding and inspection

(6) End-plug joining test applying PRW technique

(7) Evaluation of irradiation behavior

(8) Mechanical properties after neutron irradiation

Authentication

(10)Properties of Frozen Body of Melted Debris Containing UO₂

(12) Formation and dissolution behavior of SrZrO₃