Oral presentation

[2D01-05] ATF, Irradiation Behavior of Water Reactor Fuel

Thu. Sep 8, 2022 2:45 PM - 4:05 PM Room D (E1 Bildg.2F No.23)

Chair:Akihiro Suzuki(NFD)

2:45 PM - 3:00 PM

[2D01] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(9) Joint Strength Evaluation of End-plug Joints in SiC Tubes at A Sumilated Severe Accident (2)

*Ryo Ishibashi¹, Kazuma Hirosaka¹, Masatoshi Shibata¹, Masana Sasaki¹, Akiyuki Tsuchiya¹, Yoshiyuki Nemoto² (1. HGNE, 2. JAEA)

3:00 PM - 3:15 PM

[2D02] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1) Intermediate review on a reactor safety evaluation and updated development road map

*Nozomu Murakami¹, Masaaki Yamato¹, Daiki Sato², Yuji Okada² (1. MHI, 2. MNF)

3:15 PM - 3:30 PM

[2D03] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2) High temperature oxidation and corrosion behaviour

*Yuji Okada¹, Daiki Sato¹, Nozomu Murakami², Yasunari Shinohara³, Koichi Ogata³ (1. MNF, 2. MHI, 3. NDC)

3:30 PM - 3:45 PM

[2D04] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(5) Effect of irradiation temperature on element concentration in SPPs of Zr-0.5Nb model alloy under Zr ion irradiation

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

3:45 PM - 4:00 PM

[2D05] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(6) Effect of irradiation temperature on element concentration in a matrix of Zr-0.5Nb model alloy under Zr ion irradiation

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

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

Oral presentation

[2D06-08] Fuel Behavior in Accident, Nitride Fuel

Thu. Sep 8, 2022 4:05 PM - 4:55 PM Room D (E1 Bildg.2F No.23)

Chair:Fumihiro Nakamori(CRIEPI)

4:05 PM - 4:20 PM

[2D06] Study on the failure behavior of high-burnup fuels under reactivity initiated accident conditions

Analyses of the failure mode change observed on a PWR-MOX fuel and its occurrence condition

*Yoshinori Taniguchi¹, Takeshi Mihara¹, Kazuo Kakiuchi¹, Shun Hakamatsuka¹, Takuya Yoshida¹, Yutaka Udagawa¹ (1. JAEA)

4:20 PM - 4:35 PM

[2D07] Chemical interaction of CsOH vapor with UO₂ and Fe-Zr melts

*Kunihisa Nakajima¹, Masahide Takano¹ (1. JAEA)

4:35 PM - 4:50 PM

[2D08] Steam oxidation tests of uranium nitride fuels with additives

*Kyosuke Shibasaki¹, Shigeru Kurematsu¹, Nozomu Murakami² (1. MHI Nuclear Development Corporation, 2. MHI)

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

Oral presentation

[2D09-11] Aging Properties of Fuel Debris

Thu. Sep 8, 2022 4:55 PM - 5:45 PM Room D (E1 Bildg.2F No.23)

Chair:Kunihisa Nakajima(JAEA)

4:55 PM - 5:10 PM

[2D09] Development of Estimation Technology of Aging Properties of Fuel Debris

(1)Research plan focusing on the radioactive microparticle generation by the chemical aging

*Shohei Kawano¹, Yoshiyuki Kawaharada¹, Shinya Miyamoto¹, Akihiro Suzuki², Yusuke Miura² (1. TOSHIBA ESS, 2. NFD)

5:10 PM - 5:25 PM

[2D10] Development of Estimation Technology of Aging Properties of Fuel Debris

(2) Fabrication of the simulated fuel debris with the chemical factor generating microparticles

*Akihiro Suzuki¹, Norio Kawashima¹, Yusuke Miura¹, Atsushi Ohuchi¹, Yoshiyuki Kawaharada², Shohei Kawano² (1. NFD, 2. Toshiba ESS)

5:25 PM - 5:40 PM

[2D11] Development of Estimation Technology of Aging Properties of Fuel Debris

(3) (3) Accelerated water sintering and air oxidizing testing on the chemical aging of simulated fuel debris.

*Yusuke Miura¹, Akihiro Suzuki¹, Yoshiyuki Kawaharada², Shinya Miyamoto², Shohei Kawano² (1. NFD, 2. Toshiba ESS)

Time reserved for Chair （5:40 PM - 5:45 PM）

Sessions

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

[2D01-05] ATF, Irradiation Behavior of Water Reactor Fuel

[2D01] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(9) Joint Strength Evaluation of End-plug Joints in SiC Tubes at A Sumilated Severe Accident (2)

[2D02] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(1) Intermediate review on a reactor safety evaluation and updated development road map

[2D03] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR

(2) High temperature oxidation and corrosion behaviour

[2D04] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(5) Effect of irradiation temperature on element concentration in SPPs of Zr-0.5Nb model alloy under Zr ion irradiation

[2D05] Evaluation of irradiation effects on microstructure and element distribution in Nb-doped Zr alloys

(6) Effect of irradiation temperature on element concentration in a matrix of Zr-0.5Nb model alloy under Zr ion irradiation

[2D06-08] Fuel Behavior in Accident, Nitride Fuel

[2D06] Study on the failure behavior of high-burnup fuels under reactivity initiated accident conditions

Analyses of the failure mode change observed on a PWR-MOX fuel and its occurrence condition

[2D07] Chemical interaction of CsOH vapor with UO₂ and Fe-Zr melts

[2D08] Steam oxidation tests of uranium nitride fuels with additives

[2D09-11] Aging Properties of Fuel Debris

[2D09] Development of Estimation Technology of Aging Properties of Fuel Debris

(1)Research plan focusing on the radioactive microparticle generation by the chemical aging

[2D10] Development of Estimation Technology of Aging Properties of Fuel Debris

(2) Fabrication of the simulated fuel debris with the chemical factor generating microparticles

[2D11] Development of Estimation Technology of Aging Properties of Fuel Debris

(3) (3) Accelerated water sintering and air oxidizing testing on the chemical aging of simulated fuel debris.

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