Oral presentation

[1E01-06] External Event

Wed. Sep 8, 2021 10:15 AM - 11:55 AM Room E

chair: Atsushi Ui (CRIEPI)

10:15 AM - 10:30 AM

[1E01] Study on local damage to reinforced concrete panels subjected to oblique impact by projectiles

Part1: Outline of impact test

*Akemi Nishida¹, Zuoyi Kang¹, Yukihiko Okukda¹, Haruji Tsubotaa¹, Yinsheng Li¹ (1. JAEA)

10:30 AM - 10:45 AM

[1E02] Study on local damage to reinforced concrete panels subjected to oblique impact by projectiles

Part2: Test results

*Zuoyi Kang¹, Yukihiko Okuda¹, Akemi Nishida¹, Haruji Tsubota¹, Yinsheng Li¹ (1. Japan Atomic Energy Agency)

10:45 AM - 11:00 AM

[1E03] Study on assessment of effects on reinforced concrete structure with internal equipment subjected to projectile impact

Part1: Impact test on a reinforced concrete structure with internal pseudo equipment subjected to projectile impact

*Yukihiko Okuda¹, Zuoyi Kang¹, Akemi Nishida¹, Haruji Tsubota¹, Yinsheng Li¹ (1. JAEA)

11:00 AM - 11:15 AM

[1E04] Proposals of No-Collapse Tsunami Levee for Atomic Power Plants against Un-expected Design-size of Tsunami Waves

*Daijiro Kaneko¹ (1. Remote Sensing Environmental Monitor, Inc.)

11:15 AM - 11:30 AM

[1E05] Development of the automation tool for wildfire evaluation with FARSITE

Full automation by embedding FARSITE, and tool expansion

*Kota Tominaga¹, Hisayuki Kyou¹, Daisuke Fujiwara¹, Ryunosuke Yamaguchi¹, Hiroyuki Fujita¹ (1. TEPSYS)

11:30 AM - 11:45 AM

[1E06] Development of Business Continuity Plan Considering the Compound Risk of Nuclear Accidents Based on IRIDM

*Hirotaka Araki¹, Keita Yamamoto¹, Kenta Murakami² (1. Nagaoka Univ. of Tech., 2. UTokyo)

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

Oral presentation

[1E07-11] Severe Accident1

Wed. Sep 8, 2021 2:45 PM - 4:10 PM Room E

chair: Takahiro Arai (CRIEPI)

2:45 PM - 3:00 PM

[1E07] Development of Passive Debris Cooling System Phase II

(3)Erosion Resistance of ZrO₂ Refractories

*Satoru Kuboya¹, Yuya Takahashi¹, Shohei Kanamura¹, Keisuke Tsukada¹, Yasushi Yamamoto¹, Hideki Horie¹, Yoichi Onitsuka¹, Mika Tahara¹, Tadashi Fujii², Takumi Yoshikawa³ (1. TOSHIBA ESS, 2. HGNE, 3. JAPC)

3:00 PM - 3:15 PM

[1E08] Development of Passive Debris Cooling System Phase II

(4)Optimization of Refractory Material Laying Structure

*Tomonori Kimura¹, Masafumi Nojima¹, Tadashi Fujii¹, Yoichi Onitsuka², Takumi Yoshikawa³ (1. HGNE, 2. TOSHIBA ESS, 3. JAPC)

3:15 PM - 3:30 PM

[1E09] Development of Passive Debris Cooling System Phase II

(5)Validation of Suppressing Molten Core – Concrete Interaction

*Keisuke Tsukada¹, Yasushi Yamamoto¹, Hideki Horie¹, Satoru Kuboya¹, Yuya Takahashi¹, Shohei Kanamura¹, Yoichi Onitsuka¹, Mika Tahara¹, Tadashi Fujii², Takumi Yoshikawa³ (1. TOSHIBA ESS, 2. HGNE, 3. JAPC)

3:30 PM - 3:45 PM

[1E10] Development of Passive Debris Cooling System Phase II

(6)Construction of evaluation method

*Hideki Horie¹, Keisuke Tsukada¹, Yasushi Yamamoto¹, Mika Tahara¹, Satoru Kuboya¹, Yuya Takahashi¹, Shohei Kanamura¹, Yoichi Onitsuka¹, Tadashi Fujii², Takumi Yoshikawa³ (1. TOSHIBA ESS, 2. HGNE, 3. JAPC)

3:45 PM - 4:00 PM

[1E11] Development of Passive Debris Cooling System Phase II

(7)Applicability Evaluation

*Mika Tahara¹, Satoru Kuboya¹, Yuya Takahashi¹, Shohei Kanamura¹, Keisuke Tsukada¹, Yasushi Yamamoto¹, Hideki Horie¹, Yoichi Onitsuka¹, Tadashi Fujii², Takumi Yoshikawa³ (1. TOSHIBA ESS, 2. HGNE, 3. JAPC)

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

Oral presentation

[1E12-14] Severe Accident2

Wed. Sep 8, 2021 4:10 PM - 5:05 PM Room E

chair: Hiroshi Madokoro (JAEA)

4:10 PM - 4:25 PM

[1E12] Development of out of pile experimental method for evaluating the effect of dispersed fuel fragments on the fuel coolability depending on accumulation mode under FFRD condition

*Yuki Shimizu¹, Koichi Ogata¹, Yasunari Shinohara¹, Masaaki Yamato² (1. NDC, 2. MHI)

4:25 PM - 4:40 PM

[1E13] Numerical analysis of IVR code benchmark by MAAP5

*Kazuyuki Katsuragi¹, Naoya Hayashi¹, Kenichiro Ueda¹, Noboru Matsui¹ (1. MHI)

4:40 PM - 4:55 PM

[1E14] Prediction of core water injection timing at the time of Fukushima accident considering Tellurium release event during Zr cladding oxidation

*Akihide Hidaka^1,2, Sigeto Kawashima³, Mizuo Kajino⁴, Sentaro Takahashi⁵, Tomoyuki Takahashi³ (1. Japan Atomic Energy Agency, 2. Khalifa Univ., 3. Kyoto Univ., 4. Meteorological Research Institute, 5. Former Kyoto Univ.)

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

Oral presentation

[2E01-04] Next Generation Reactor Safety 1

Thu. Sep 9, 2021 9:30 AM - 10:35 AM Room E

chair: Kenji Kamiyama (JAEA)

9:30 AM - 9:45 AM

[2E01] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(3)Overview of overall project progress through FY2020

*Koji Morita¹, Wei Liu¹, Tatsumi Arima¹, Yuji Arita², Isamu Sato³, Haruaki Matsuura³, Yoshihiro Sekio⁴, Hiroshi Sagara⁵, Masatoshi Kawashima⁵ (1. Kyushu Univ., 2. Univ. of Fukui, 3. TCU, 4. JAEA, 5. Tokyo Tech)

9:45 AM - 10:00 AM

[2E02] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(4)Selection and material property evaluation for simulated fuel and fusible plug materials

*Isamu Sato¹, Kokin Oo¹, Daisuke Yamada¹, Yuji Arita², Kei Ando², Koharu Kawase², Tatsumi Arima³, Koji Morita³ (1. Tokyo City Univ., 2. Univ. of Fukui, 3. Kyushu Univ.)

10:00 AM - 10:15 AM

[2E03] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(5)The device structure concept and Basic evaluations of fuel migration behavior in the device by visualization experiments

*Yoshihiro Sekio¹, Isamu Sato², Masatoshi Kawashima³, Koji Morita⁴ (1. JAEA, 2. TCU, 3. Tokyo Tech, 4. Kyushu Univ.)

10:15 AM - 10:30 AM

[2E04] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(6)Specification of the device assembly design effective in the reactivity control by its material relocation

*Hiroshi Sagara¹, Koji Morita², Masatoshi Kawashima¹, Tatsumi Arima², Wei Liu², Yuji Arita³, Isamu Sato⁴ (1. Tokyo Tech, 2. Kyushu Univ., 3. Univ. of Fukui, 4. TCU)

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

Oral presentation

[2E05-09] Next Generation Reactor Safety 2

Thu. Sep 9, 2021 10:35 AM - 12:00 PM Room E

chair: Tohru Suzuki (TCU)

10:35 AM - 10:50 AM

[2E05] A study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool

(1)Water simulation test for bubble rising behavior

*Munemichi Kawaguchi¹, Shinya Miyahara¹, Hiroshi Seino², Takuto Atsumi¹, Masayoshi Uno¹ (1. University of Fukui, 2. Japan Atomic Energy Agency)

10:50 AM - 11:05 AM

[2E06] A study on removal mechanisms of cesium aerosol from noble gas bubble in sodium pool

(2)Comparison of water simulation test results with calculation results of AESOP code

*Shinya Miyahara¹, Munemichi Kawaguchi¹, Hiroshi Seino², Takuto Atsumi¹, Masayoshi Uno¹ (1. Research Institute of Nuclear Engineering, University of Fukui, 2. Japan Atomic Energy Agency)

11:05 AM - 11:20 AM

[2E07] Particle-based simulation of jet impingement behaviors

*Daichi Takatsuka¹, Takeshi Nakamura¹, Ting Zhang¹, Wei Liu¹, Koji Morita¹, Kenji Kamiyama² (1. Kyushu Univ., 2. JAEA)

11:20 AM - 11:35 AM

[2E08] Development of detailed fuel pin model in SIMMER-V code

(1)Development of the prototype model and verification plan

*Shinya Ishida¹, Hirotaka Tagami¹, Yoshitaka Fukano¹, Hidemasa Yamano¹, Shigenobu Kubo¹ (1. JAEA)

11:35 AM - 11:50 AM

[2E09] Transient Analysis Code for Molten Salt Reactor: DYMOS

Yoichiro Shimazu², *Ritsuo Yoshioka¹, Koji Ogasawara¹, Masaaki Furukawa³ (1. International Thorium Molten-Salt Forum, 2. University of Fukui, 3. Thorium Tech Solution Inc.)

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

Oral presentation

[2E10-14] Next Generation Reactor Safety 3

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

chair: Isamu Sato (TCU)

2:45 PM - 3:00 PM

[2E10] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(25)Project Overview and Progress until 2020

*Hidemasa Yamano¹, Toshihide Takai¹, Yuki Emura¹, Hideo Higashi², Hiroyuki Fukuyama², Tsuyoshi Nishi³, Koji Morita⁴, Kinya Nakamura⁵, Hirofumi Fukai⁶, Marco Pellegrini⁷ (1. JAEA, 2. Tohoku Univ., 3. Ibaraki Univ., 4. Kyushu Univ., 5. CRIEPI, 6. Waseda Univ., 7. UTokyo)

3:00 PM - 3:15 PM

[2E11] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(26)Density and Surface Tension of 15mass%B₄C-SS Eutectic Molten Materials

*Hiroyuki Fukuyama¹, Hideo Higashi¹, Hidemasa Yamano² (1. Tohoku Univ., 2. JAEA)

3:15 PM - 3:30 PM

[2E12] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(27)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 15mass%B₄C-SS Eutectic Molten Material

*Hideo Higashi¹, Hiroyuki Fukuyama¹, Hidemasa Yamano² (1. Tohoku Univ., 2. JAEA)

3:30 PM - 3:45 PM

[2E13] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(28)Three-dimensional Raman spectroscopic analysis of B₄C-SS and FeB-SS eutectic melt

*Hirofumi Fukai¹, Masahiro Furuya¹, Hidetoshi Morita¹, Hidemasa Yamano² (1. Waseda Univ., 2. JAEA)

3:45 PM - 4:00 PM

[2E14] Study on discharge behavior of molten core materials in core disruptive accidents of sodium cooled fast reactors

Analysis on discharge behavior through a sodium-filled channel with an internal structure

*Shinya Kato¹, Kenichi Matsuba¹, Kenji Kamiyama¹ (1. JAEA)

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

Oral presentation

[2E15-20] SMR, Accident Evaluation Models & Power Distribution Estimation

Thu. Sep 9, 2021 4:10 PM - 5:50 PM Room E

chair: Yoshiro Nishioka (Toshiba ESS)

4:10 PM - 4:25 PM

[2E15] Development of Small Modular LWRs for Multi-Purpose Use

Development of Passive Core Cooling System

*Naoaki Hirota¹, Tomoyuki Kitani¹, Yoshihiko Kataoka¹, Hiroshi Taniguchi¹ (1. MHI)

4:25 PM - 4:40 PM

[2E16] Study of downstream effect of the sump screen for post LOCA long term core cooling

(5)Element test of flow path feeding coolant at the core inlet (Effect evaluation of test parameters)

*Kei Higashi¹, Tomoaki Ogata¹, Ryo Fukuda¹, Hideyuki Sakata¹, Yugen Shiratsuchi¹, Junji Hamano² (1. MHI, 2. KEPCO)

4:40 PM - 4:55 PM

[2E17] Uncertainty of model selection based on information criteria

A case study on probability estimation model for fuel fracture during LOCA

*Takafumi Narukawa¹, Yutaka Udagawa¹ (1. JAEA)

4:55 PM - 5:10 PM

[2E18] Modeling an interface system LOCA in the severe accident analysis code “ MAAP”

*Takayoshi Kusunoki¹, Takaki Toshiya¹ (1. INSS)

5:10 PM - 5:25 PM

[2E19] Advancement of the spent fuel pool temperature evaluation in Onagawa NPPs

*Yuhei Hamada¹, Iichi Kimura¹, Hiroaki Seino¹, Hiroaki Kikkawa¹, Tomoya Shindo¹, Kenta Matsuura¹, Masashi Shimanaka¹, Toshiaki Wakabayashi¹ (1. Tohoku-EPCO)

5:25 PM - 5:40 PM

[2E20] Review of Method for Estimating Most Probable Power Distribution in BWRs by Least Squres Method Using In-core Measurements (2)

*Hideo Ezure¹ (1. Nippon Advanced Information Service)

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

Sessions

IV. Nuclear Plant Technologies » 402-1 Nuclear Safety Engineering (Safety Design, Safety Assessment/Analysis, Management)

[1E01-06] External Event

Part1: Outline of impact test

Part2: Test results

Part1: Impact test on a reinforced concrete structure with internal pseudo equipment subjected to projectile impact

Full automation by embedding FARSITE, and tool expansion

[1E07-11] Severe Accident1

(3)Erosion Resistance of ZrO2 Refractories

(4)Optimization of Refractory Material Laying Structure

(5)Validation of Suppressing Molten Core – Concrete Interaction

(6)Construction of evaluation method

(7)Applicability Evaluation

[1E12-14] Severe Accident2

[2E01-04] Next Generation Reactor Safety 1

(3)Overview of overall project progress through FY2020

(4)Selection and material property evaluation for simulated fuel and fusible plug materials

(5)The device structure concept and Basic evaluations of fuel migration behavior in the device by visualization experiments

(6)Specification of the device assembly design effective in the reactivity control by its material relocation

[2E05-09] Next Generation Reactor Safety 2

(1)Water simulation test for bubble rising behavior

(2)Comparison of water simulation test results with calculation results of AESOP code

(1)Development of the prototype model and verification plan

[2E10-14] Next Generation Reactor Safety 3

(25)Project Overview and Progress until 2020

(26)Density and Surface Tension of 15mass%B4C-SS Eutectic Molten Materials

(27)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 15mass%B4C-SS Eutectic Molten Material

(28)Three-dimensional Raman spectroscopic analysis of B4C-SS and FeB-SS eutectic melt

Analysis on discharge behavior through a sodium-filled channel with an internal structure

[2E15-20] SMR, Accident Evaluation Models & Power Distribution Estimation

Development of Passive Core Cooling System

(5)Element test of flow path feeding coolant at the core inlet (Effect evaluation of test parameters)

A case study on probability estimation model for fuel fracture during LOCA

Authentication

(3)Erosion Resistance of ZrO₂ Refractories

(26)Density and Surface Tension of 15mass%B₄C-SS Eutectic Molten Materials

(27)Normal Spectral Emissivity, Heat Capacity and Thermal Conductivity of 15mass%B₄C-SS Eutectic Molten Material

(28)Three-dimensional Raman spectroscopic analysis of B₄C-SS and FeB-SS eutectic melt