Oral presentation

[2D01-04] Irradiation & Accident Behavior of LWR Fuel

Thu. Sep 9, 2021 9:30 AM - 10:45 AM Room D

chair: Kan Sakamoto (NFD)

9:30 AM - 9:45 AM

[2D01] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(1)TEM-EDS analysis of Zr-0.5Nb alloy after Zr ion irradiation

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

9:45 AM - 10:00 AM

[2D02] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(2)Atom probe analysis of Zr-0.5Nb alloy after Zr ion irradiation

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

10:00 AM - 10:15 AM

[2D03] Evaluation of mechanical properties of fuel cladding tubes using nanoindentation

*Akihiro Yamauchi¹, Kazuo Kakiuchi², Yutaka Udagawa², Koji Kitano¹ (1. S/NRA/R, 2. JAEA)

10:15 AM - 10:30 AM

[2D04] RIA-simulated experiments on high-burnup BWR fuel and PWR-MOX fuel

Follow-up study on causes of the recently observed low-enthalpy failure and failure mode change

*Takeshi Mihara¹, Yoshinori Taniguchi¹, Yoshiya Akiyama¹, Yasuyuki Muramatsu¹, Koji Usami¹, Takuya Yoshida¹, Yutaka Udagawa¹ (1. JAEA)

Time reserved for Chair （10:30 AM - 10:45 AM）

Oral presentation

[2D05-08] Accident Tolerant Fuel

Thu. Sep 9, 2021 10:45 AM - 12:00 PM Room D

chair: Fumihiro Nakamori (CRIEPI)

10:45 AM - 11:00 AM

[2D05] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(8)Joint Strength Evaluation of End-plug Joints in SiC Tubes at A Sumilated Severe Accident

*Ryo Ishibashi¹, Kazuma Hirosaka¹, Teppei Yamana¹, Masatoshi Shibata¹, Masana Sasaki¹, Takao Kondo¹ (1. HGNE)

11:00 AM - 11:15 AM

[2D06] R&D of advanced stainless steels for BWR fuel claddings (6)

*Kan Sakamoto¹, Junya Kaneda², Shinichi Asamoto³, Masana Sasaki², Takao Kondo² (1. NFD, 2. HGNE, 3. GNF-J)

11:15 AM - 11:30 AM

[2D07] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1)Coated cladding performance at accident conditions

*Nozomu Murakami¹, Takanori Yumura¹, Masaaki Onoue¹, Daiki Sato², Yuji Okada², Seiichi Watanabe² (1. MHI, 2. MNF)

11:30 AM - 11:45 AM

[2D08] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2)Manufacturing test

*Yuji Okada¹, Daiki Sato¹, Nozomu Murakami² (1. MNF, 2. MHI)

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

Oral presentation

[2D09-13] Development of Fast Reactor Fuel

Thu. Sep 9, 2021 2:45 PM - 4:10 PM Room D

chair: Yuji Arita (Univ. of Fukui)

2:45 PM - 3:00 PM

[2D09] Thermo-physical properties of the alloy called fusible plug in passive reactor shutdown device

*Masato Sumiyoshi¹, Tatsumi Arima¹, Kazuya Idemitsu¹, Yaohiro Inagaki¹, Kouzi Morita¹ (1. Kyushu Univ.)

3:00 PM - 3:15 PM

[2D10] Measurement of melting temperature on MOX containing Np

*Shun Hirooka¹, Shinya Nakamichi¹, Masato Kato¹, Daisuke Sato², Naoya Furusawa² (1. JAEA, 2. Inspection Development)

3:15 PM - 3:30 PM

[2D11] Demonstration research on fast reactor recycling using low decontaminated MA- bearing MOX fuels

(7)Accuracy of local melting point measurement for fuel pellet using laser heating

*Tadahiro Joraku¹, Nanase Fukushima¹, Tatsumi Arima¹, Yaohiro Inagaki¹, Kazuya Idemitsu¹, Masato Kato² (1. Kyushu Univ., 2. JAEA)

3:30 PM - 3:45 PM

[2D12] Advancement of detailed core bowing analysis code for fast reactor

(3)Validity of calculation code by IAEA benchmark problem of the duct bowing experiment

*Koji Kusumi¹, Hirokazu Ohta¹, Kazuya Ohgama², Hidemasa Yamano², Satoshi Futagami² (1. CRIEPI, 2. JAEA)

3:45 PM - 4:00 PM

[2D13] Study on powder adhesion prevention by surface micro-fabrication of stainless steel

*Kohei Hayashizaki¹, Koyo Omi¹, Tomoomi Segawa¹, Koichi Kawaguchi¹, Katsunori Ishii¹, Hiroshi Satone², Michitaka Suzuki² (1. JAEA, 2. Univ. of Hyogo)

Time reserved for Chair （4:00 PM - 4:10 PM）

Sessions

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

[2D01-04] Irradiation & Accident Behavior of LWR Fuel

[2D01] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(1)TEM-EDS analysis of Zr-0.5Nb alloy after Zr ion irradiation

[2D02] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(2)Atom probe analysis of Zr-0.5Nb alloy after Zr ion irradiation

[2D03] Evaluation of mechanical properties of fuel cladding tubes using nanoindentation

[2D04] RIA-simulated experiments on high-burnup BWR fuel and PWR-MOX fuel

Follow-up study on causes of the recently observed low-enthalpy failure and failure mode change

[2D05-08] Accident Tolerant Fuel

[2D05] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(8)Joint Strength Evaluation of End-plug Joints in SiC Tubes at A Sumilated Severe Accident

[2D06] R&D of advanced stainless steels for BWR fuel claddings (6)

[2D07] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1)Coated cladding performance at accident conditions

[2D08] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2)Manufacturing test

[2D09-13] Development of Fast Reactor Fuel

[2D09] Thermo-physical properties of the alloy called fusible plug in passive reactor shutdown device

[2D10] Measurement of melting temperature on MOX containing Np

[2D11] Demonstration research on fast reactor recycling using low decontaminated MA- bearing MOX fuels

(7)Accuracy of local melting point measurement for fuel pellet using laser heating

[2D12] Advancement of detailed core bowing analysis code for fast reactor

(3)Validity of calculation code by IAEA benchmark problem of the duct bowing experiment

[2D13] Study on powder adhesion prevention by surface micro-fabrication of stainless steel

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