Oral presentation

[1E01-07] Accident Tolerant Fuel

Wed. Sep 16, 2020 10:00 AM - 12:00 PM Room E (Zoom room 5)

Chair:Kazuo Kakiuchi(JAEA)

10:00 AM - 10:15 AM

[1E01] R&D for introducing silicon carbide materials to safety improvement of BWR's core

(7)Oxidation kinetics of SiC at 1400-1600^oC under different steam flow rate

*Hai V. Pham¹, Yuji Nagae¹, Masaki Kurata¹, Ryou Ishibashi² (1. JAEA, 2. HGNE)

10:15 AM - 10:30 AM

[1E02] R&D for Introducing Silicon Carbide Materials to Safety Improvement of BWR’s Core

(6)Hydrothermal Corrosion and High-temperature Steam Oxidation Behavior of Corrosion-resistant-coated SiC

*Ryo Ishibashi¹, Tomohiko Ikegawa¹, Masatoshi Shibata¹, Masana Sasaki¹, Takao Kondo¹ (1. HGNE)

10:30 AM - 10:45 AM

[1E03] Development of coated zirconium alloy fuel cladding as an accident tolerant fuel for PWR
(1) Design cocept and initial results of basic performance tests

*Nozomu Murakami¹, Masaaki Onoue¹, Kentaro Tanaka¹, Seiichi Watanabe², Daiki Sato², Yuji Okada² (1. MHI, 2. MNF)

10:45 AM - 11:00 AM

[1E04] R&D of advanced stainless steels for BWR fuel claddings (5)

(1)Barrier effect of oxide layer on tritium permeation

*KAN SAKAMOTO¹, Kenichi Hashizume², Shinichiro Yamashita³ (1. NFD, 2. Kyushu Univ., 3. JAEA)

11:00 AM - 11:15 AM

[1E05] R&D of advanced stainless steels for BWR fuel claddings (5)

(2)Applicability of 10x10 fuel design

*Akihiko Sawada¹, Kazuyuki Kusagaya¹, Kan Sakamoto² (1. GNF-J, 2. NFD)

11:15 AM - 11:30 AM

[1E06] R&D of advanced stainless steels for BWR fuel claddings (5)

(3)Change of microstructures by neutron irradiation

*Naoko OONO-HORI¹, Naoyuki HASHIMOTO¹, Takeshi TOYAMA², Shigeharu UKAI¹, Kan SAKAMOTO³, Shinichiro YAMASHITA⁴ (1. Hokkaido Univ., 2. Tohoku Univ., 3. NFD, 4. JAEA)

11:30 AM - 11:45 AM

[1E07] R&D of advanced stainless steels for BWR fuel claddings (5)

(4)Detail evaluation of oxidation behaviour

*Yoshiyuki Nemoto¹, Yuki Fujimura¹, Kan Sakamoto², Shinichiro Yamashita¹ (1. JAEA, 2. NFD)

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

Oral presentation

[1E10-15] Analysis of Fuel Debris and Decommissioning Technology

Wed. Sep 16, 2020 3:25 PM - 5:05 PM Room E (Zoom room 5)

Chair:Tatsumi Arima(Kyushu Univ.)

3:25 PM - 3:40 PM

[1E10] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(21)Outline of the research and achievement of the study on fuel debris analysis

*Masayoshi Uno¹, Yuji Ohishi², Osamu Kuwaduru¹, Kozo Katsuyama³, Yuji Arita¹, Tatumi Arima⁴ (1. University of Fukui, 2. Osaka University, 3. Japan Atomic Energy Agency, 4. Kyusyu University)

3:40 PM - 3:55 PM

[1E11] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(22)Physical properties of UO₂-B₂O₃/ZrO₂-Al₂O₃/ZrB₂made by eutectic reaction

*Shintaro Yoshida¹, Takashi Onitsuka¹, Masayoshi Uno¹ (1. UNIVERSITY OF FUKUI)

3:55 PM - 4:10 PM

[1E12] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(23) Mechanical properties of melt-solidified fuel debris simulants fabricated using eutectic reactions

*Takashi Onitsuka¹, Shintaro Yoshida¹, Masami Uno¹ (1. Univ. of Fukui)

4:10 PM - 4:25 PM

[1E13] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(24)Evaluation of compressive strength of melted-solidified ceramics by damage mechanics finite element analysis

*Osamu Kuwazuru¹, Yohei Nosaka¹, Masaki Teranishi² (1. Univ. of Fukui, 2. Niigata Univ.)

4:25 PM - 4:40 PM

[1E14] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(25)Porosity evaluation of simulated fuel debris using X-ray computed tomography

*Tien-Hsiu Tsai¹, Akihiro Ishimi¹, Kozo Katsuyama¹, Masayoshi Uno² (1. JAEA, 2. Univ. of Fukui)

4:40 PM - 4:55 PM

[1E15] Research and human resource development for analysis of fuel debris and decommissioning technology of Fukushima Daiichi nuclear power plants

(26)Behavioral Assessment of CsFeSiO₄

*Takeshi AKAMA¹, Taishi Inoue¹, Yuji Arita¹ (1. Univ. of Fukui)

Time reserved for Chair （4:55 PM - 5:05 PM）

Oral presentation

[2E08-13] Nitride fuel

Thu. Sep 17, 2020 2:45 PM - 4:25 PM Room E (Zoom room 5)

Chair:Kunihiro Itoh(NDC)

2:45 PM - 3:00 PM

[2E08] R&D on Nitride Fuel Ctcle for MA Transmutation to Enhance Safety and Economy

(14)Dimensional Recovery of He-accumulated Nitride Pellet Containing Cm by Annealing

*Masahide Takano¹, Seiya Takaki¹ (1. JAEA)

3:00 PM - 3:15 PM

[2E09] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(15)Nitride Particles Fabrication through External Gelation and Demonstration of Nitrogen Circulation Refining System Prototype Model

*Tohma Iwasa¹, Masahide Takano¹ (1. JAEA)

3:15 PM - 3:30 PM

[2E10] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(16)Application of Pore Former for Density Control of TRU Nitride Pellets

*Seiya Takaki¹, Masahide Takano¹, Haruyoshi Otobe¹ (1. JAEA)

3:30 PM - 3:45 PM

[2E11] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(17)Solid-liquid Phase Transition Temperature of TiN and Thermodynamic Behavior of Nitride Fuels

*Tatsumi Arima¹, Toma Iwasa², Masahide Takano² (1. Kyushu Univ., 2. JAEA)

3:45 PM - 4:00 PM

[2E12] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(18)Chemical Dissolution Tests of Crushed Pieces of Simulated Nitride Fuel Samples in Molten Salt

*Hirokazu HAYASHI¹, Takumi SATO¹ (1. JAEA)

4:00 PM - 4:15 PM

[2E13] R&D on Nitride Fuel Cycle for MA Transmutation to Enhance Safety and Economy

(19)Electrochemical Recovery of Zr and Cd as a Pretreatment Step of Reductive Extraction

*TSUYOSHI MURAKAMI¹, MASATOSHI IIZUKA¹, HIROKAZU HAYASHI² (1. CRIEPI, 2. JAEA)

Time reserved for Chair （4:15 PM - 4:25 PM）

Oral presentation

[2E14-18] Evaluation of severe accident and Cs behavior

Thu. Sep 17, 2020 4:25 PM - 5:50 PM Room E (Zoom room 5)

Chair:Masayoshi Uno(Univ. of Fukui)

4:25 PM - 4:40 PM

[2E14] Oxidation and evaporation behaviors of Mo under a severe accident conditions

*Jiazhan LIU¹, Kunihisa NAKAJIMA¹, Shuhei MIWA¹, Hidetoshi KARASAWA¹, Masahiko Osaka¹ (1. Japan Atomic Energy Agency)

4:40 PM - 4:55 PM

[2E15] A study on the chemical reaction between fuel materials and graphite block (3) Differential scanning calorimetry of the uranium dioxide and graphite (2)

*Hiroyuki Naito¹, Masaya Yamamoto¹, Shigetaka Maeda¹, Shigeru Kurematsu², Isamu Sato³, Koji Maeda¹ (1. JAEA, 2. NDC, 3. Tokyo City Univ.)

4:55 PM - 5:10 PM

[2E16] Synthesis and characterization of cesium silicate Cs₂Si₄O₉

*Thi Mai Dung Do¹, I wayan Ngarayana¹, Hieu Duy Nguyen¹, Kenta Murakami¹, Hisayuki Suematsu¹, Manabu Koide³, Kunhisa Nakajima², Eriko Suzuki², Masahiko Osaka² (1. Nagaoka University of Technology, 2. Japan Atomic Energy Agency, 3. National Institute of Technology, Nagaoka College)

5:10 PM - 5:25 PM

[2E17] Chemical reaction behavior between cesium hydroxide and iron oxides

*Jumpei Imoto¹, Kunihisa Nakajima¹, Masahiko Osaka¹ (1. JAEA)

5:25 PM - 5:40 PM

[2E18] Basic evaluation of the release of cesium compounds from simulated fuel pellets

*Takuma Fujiwara¹, Yuji Arita¹ (1. Univ. of Fukui)

Time reserved for Chair （5:40 PM - 5:50 PM）

Oral presentation

[3E04-07] Irradiation behavior analysis

Fri. Sep 18, 2020 10:50 AM - 12:00 PM Room E (Zoom room 5)

Chair:Osamu Kuwazuru(Univ. of Fukui)

10:50 AM - 11:05 AM

[3E04] Gd-doped fuel behavior analysis modifying densification model and taking account of power change during low burnup

*Koichi Ota¹, Takanori Kameyama² (1. Course of Applied Science, Graduate School of Engineering, Tokai University, 2. Tokai University)

11:05 AM - 11:20 AM

[3E05] Preliminary Study of Fission Gas Release Model for MOX Fuels with Treatment of Heterogeneous Microstructure

*Yudai Tasaki¹, Yutaka Udagawa¹, Masaki Amaya¹ (1. Japan Atomic Energy Agency)

11:20 AM - 11:35 AM

[3E06] Effect of hydrogen absorption on irradiation growth of Zircaloy-4 cladding tube

*Kazuo Kakiuchi¹, Masaki Amaya¹ (1. JAEA)

11:35 AM - 11:50 AM

[3E07] Observation of fracture surface of Zr hydride

*Hideaki Sanenobu¹, Yuji Ohishi¹, Hiroaki Muta¹ (1. Osaka Univ.)

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

Sessions

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

[1E01-07] Accident Tolerant Fuel

(7)Oxidation kinetics of SiC at 1400-1600oC under different steam flow rate

(6)Hydrothermal Corrosion and High-temperature Steam Oxidation Behavior of Corrosion-resistant-coated SiC

(1)Barrier effect of oxide layer on tritium permeation

(2)Applicability of 10x10 fuel design

(3)Change of microstructures by neutron irradiation

(4)Detail evaluation of oxidation behaviour

[1E10-15] Analysis of Fuel Debris and Decommissioning Technology

(21)Outline of the research and achievement of the study on fuel debris analysis

(22)Physical properties of UO2-B2O3/ZrO2-Al2O3/ZrB2 made by eutectic reaction

(23) Mechanical properties of melt-solidified fuel debris simulants fabricated using eutectic reactions

(24)Evaluation of compressive strength of melted-solidified ceramics by damage mechanics finite element analysis

(25)Porosity evaluation of simulated fuel debris using X-ray computed tomography

(26)Behavioral Assessment of CsFeSiO4

[2E08-13] Nitride fuel

(14)Dimensional Recovery of He-accumulated Nitride Pellet Containing Cm by Annealing

(15)Nitride Particles Fabrication through External Gelation and Demonstration of Nitrogen Circulation Refining System Prototype Model

(16)Application of Pore Former for Density Control of TRU Nitride Pellets

(17)Solid-liquid Phase Transition Temperature of TiN and Thermodynamic Behavior of Nitride Fuels

(18)Chemical Dissolution Tests of Crushed Pieces of Simulated Nitride Fuel Samples in Molten Salt

(19)Electrochemical Recovery of Zr and Cd as a Pretreatment Step of Reductive Extraction

[2E14-18] Evaluation of severe accident and Cs behavior

[3E04-07] Irradiation behavior analysis

Authentication

(7)Oxidation kinetics of SiC at 1400-1600^oC under different steam flow rate

(22)Physical properties of UO₂-B₂O₃/ZrO₂-Al₂O₃/ZrB₂made by eutectic reaction

(26)Behavioral Assessment of CsFeSiO₄