Oral presentation

[1O01-04] SFR 1

Wed. Sep 6, 2023 10:00 AM - 11:05 AM Room O (School of Eng. Bildg. 2F 522)

Chair:Hidetoshi Karasawa(JAEA)

10:00 AM - 10:15 AM

[1O01] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(32) Project Overview and Progress until 2022

*Hidemasa Yamano¹, Toshihide Takai¹, Yuki Emura¹, Hideo Higashi², Hiroyuki Fukuyama², Koji Morita³, Kinya Nakamura⁴, Zeeshan Ahmed⁵, Marco Pellegrini⁵, Tsuyoshi Nishi⁶ (1. Japan Atomic Energy Agency, 2. Tohoku Univ., 3. Kyushu Univ., 4. CRIEPI, 5. Tokyo Univ., 6. Ibaraki Univ.)

10:15 AM - 10:30 AM

[1O02] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(33) Corrosion behavior of B₄C pellet immersed in molten stainless steel

*Toshihide Takai¹, Yuki Emura, Hidemasa Yamano (1. JAEA)

10:30 AM - 10:45 AM

[1O03] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(34) Ultra-high temperature thermal analysis of SUS316L containing 14, 17mass%B₄C using blackbody radiation during melting and solidification

*Hideo Higashi¹, Makoto Ohtsuka¹, Masayoshi Adachi¹, Hiroyuki Fukuyama¹, Hidemasa Yamano² (1. Tohoku Univ., 2. JAEA)

10:45 AM - 11:00 AM

[1O04] Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors

(35) Solidification process of SUS316L containing 14, 17mass%B₄C by combination of in-situ observation and rapid cooling with electromagnetic levitation method

*Hiroyuki Fukuyama¹, Hideo Higashi¹, Makoto Ohtsuka¹, Masayoshi Adachi¹, Hidemasa Yamano² (1. Tohoku University, 2. JAEA)

Time reserved for Chair （11:00 AM - 11:05 AM）

Oral presentation

[1O05-08] SFR2

Wed. Sep 6, 2023 11:05 AM - 12:10 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Hidemasa Yamano(JAEA)

11:05 AM - 11:20 AM

[1O05] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(11) Overview of project progress

*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. Tokyo City Univ., 4. JAEA, 5. Tokyo Tech)

11:20 AM - 11:35 AM

[1O06] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(12) Measurement of thermophysical properties and evaluation of salt-based fuels

*Taku Miyabe¹, Yuji Arita¹ (1. Univ. of Fukui)

11:35 AM - 11:50 AM

[1O07] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(13) Evaluations on core performance with candidate device specifications

*Masatoshi Kawashima¹, Hiroshi Sagara¹, Koji Morita², Wei Liu², Tatsumi Arima², Yuji Arita³, Isamu Sato⁴, Haruaki Matsuura⁴, Yoshihiro Sekio⁵ (1. TI tech, 2. Kyushu Univ., 3. Univ. of Fukui, 4. Tokyo City Univ., 5. JAEA)

11:50 AM - 12:05 PM

[1O08] Development of a passive safety shutdown device to prevent core damage accidents in fast reactors

(14) Evaluations on non-proliferation features of the passive shutdown device

*sagara asgara¹, Masatoshi Kawashima¹, Koji Morita², Wei Liu², Tatsumi Arima², Yuji Arita³, Isamu Sato⁴, Haruaki Matsuura⁴, Yoshihiro Sekio⁵ (1. Tokyo Tech, 2. Kyushu Univ., 3. Univ. of Fukui, 4. Tokyo City Univ., 5. JAEA)

Time reserved for Chair （12:05 PM - 12:10 PM）

Oral presentation

[1O09-12] SFR 3

Wed. Sep 6, 2023 2:45 PM - 3:50 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Koji Morita(Kyushu Univ.)

2:45 PM - 3:00 PM

[1O09] Safety Evaluation of Decay Heat Removal Characteristics in a Pool-Type Sodium-Cooled Fast Reactor

*Minako Tokizaki¹, Akihiro Tani¹, Masato Ando², Yuichi Onoda³ (1. MFBR, 2. JAPC, 3. JAEA)

3:00 PM - 3:15 PM

[1O10] Validation Analysis on Amount of Cesium Released from Sodium Pool to The Inert Cover Gas

*Hiroki Sonoda¹, Tomoko Ishizu¹ (1. NRA)

3:15 PM - 3:30 PM

[1O11] Studies on relocation behavior of molten core materials in core disruptive accidents of sodium-cooled fast reactors

(11) Coolability of molten fuel discharged into a depth- and volume-limited sodium plenum

*Ken-ichi Matsuba¹, Shinya Kato¹, Kenji Kamiyama¹, Assan Akayev², Viktor Baklanov² (1. JAEA, 2. NNC)

3:30 PM - 3:45 PM

[1O12] Thermal analysis of hydrogen release behavior in the reaction of metallic sodium with sodium hydroxide

*Daisuke Doi¹ (1. JAEA)

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[1O13-14] Estimation of Fukushima Daiichi Accident

Wed. Sep 6, 2023 3:50 PM - 4:25 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Tsukasa Sugita(TOSHIBA ESS)

3:50 PM - 4:05 PM

[1O13] Estimation of the 1F3 Core Energy at the Time of the Major Core Slumping with Focuses on the D/W Pressure History

*Milly Yamasaki¹, Akifumi Yamaji¹ (1. Waseda Univ.)

4:05 PM - 4:20 PM

[1O14] Estimation of accident progression scenarios up to before and after hydrogen explosion at Fukushima Daiichi NPP Unit-3

*Kenichiro Nozaki¹, Penghui Chai¹, Shoichi Suehiro¹, Takeshi Honda², Masato Mizokami², Kenji Owada², Shinya Mizokami² (1. TEPSYS, 2. TEPCO HD)

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

Oral presentation

[1O15-20] Floating Reactor

Wed. Sep 6, 2023 4:25 PM - 6:00 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Kenta Murakami(UTokyo)

4:25 PM - 4:40 PM

[1O15] Development of offshore floating nuclear power

(1)Overview of the development at COCN

*Hiroyuki Nakano¹, Atsushi Ui², Chiaki Kino³, Akira Gotoh¹, Shuichi Ohmori¹, Masao Uesaka¹, Daisuke Hara⁴, Takafumi Anegawa¹ (1. TEPCO HD, 2. CRIEPI, 3. IAE, 4. Tokyo Tech)

4:40 PM - 4:55 PM

[1O16] Development of offshore floating nuclear power

(2)Results of COCN study on nuclear security

*Masayuki Kogure¹, Daisuke Hara², Hiroyuki Nakano¹, Domu Mitsuyama¹, Masao Uesaka¹ (1. TEPCO HD, 2. Tokyo Tec)

4:55 PM - 5:10 PM

[1O17] Development of offshore floating nuclear power

(3)Vital area identification and path analysis on nuclear security

*Daisuke Hara¹, Hiroshi Sagara¹ (1. Tokyo Tec)

5:10 PM - 5:25 PM

[1O18] Development of offshore floating nuclear power

(4) Preliminary estimation of passive cooling system for OFNP

*Chiaki Kino¹, Kenichi Tezuka¹, Atsushi Ui² (1. IAE, 2. CRIEPI)

5:25 PM - 5:40 PM

[1O19] Development of offshore floating nuclear power

(5)Void behavior of forced convection boiling under flow and power oscillation assuming offshore swinging

*Yutaka Ikeda¹, Shota Ueda¹, Takahiro Arai¹, Riichiro Okawa¹, Kenetsu Shirakawa¹, Atsushi Ui¹ (1. CRIEPI)

5:40 PM - 5:55 PM

[1O20] Development of offshore floating nuclear power

(6) Assessment of consequences of heaving of offshore floating nuclear power on accident progression

*Atsushi Ui¹, Yutaka Ikeda¹, Takahiro Arai¹ (1. CRIEPI)

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

Oral presentation

[2O01-06] Accident Behavior, Emergency Exercise

Thu. Sep 7, 2023 9:30 AM - 11:00 AM Room O (School of Eng. Bildg. 2F 522)

Chair:Kazuaki Kito(HGNE)

9:30 AM - 9:45 AM

[2O01] Experiments to evaluate the accumulation behavior of fuel fragments on the grid under FFRD condition

*Yuki Shimizu¹, Koichi Ogata¹, Yasunari Shinohara¹, Masaaki Yamato² (1. MHI Nuclear Development Corporation, 2. Mitsubishi Heavy Industries, Ltd.)

9:45 AM - 10:00 AM

[2O02] Role of Bubble Coalescence in Causing OSV in Subcooled Flow Boiling

*Binh Thanh Nguyen¹, Okawa Tomio, Ryoma Tsujimura (1. The University of Electro-Communication)

10:00 AM - 10:15 AM

[2O03] Evaluation of flammable gasses generated by organic materials in nuclear primary containment vessel (Part 2)

*Yukiko Furuhashi¹, Kazuhiro Koike¹, Takahiro Hoshino¹, Ryohei Endo¹, Shunichi Imai¹ (1. TEPCO HD)

10:15 AM - 10:30 AM

[2O04] Development of evaluation methods for High Energy Arcing Faults (HEAF)

(2) Study of oxidation model for Cu vapor

*Tomoaki SAKURAI¹, Hajime KABASHIMA¹, Toshihiro YOSHII² (1. NRA, 2. FMIC R&D INC.)

10:30 AM - 10:45 AM

[2O05] Impact test for steel plate subjected to consecutive impacts by rigid missiles

*KOSUKE NAMBA¹, TAKAHIRO MURAKAMI¹, YASUO HATTORI¹, YUZURU EGUCHI¹ (1. CRIEPI)

10:45 AM - 11:00 AM

[2O06] Analysis based on Mihama emergency exercise scenario of Kansai Electric Power Co., Inc. 2022

*Ikuo Kawasaki¹, Toshiya Takaki¹, Takumi Kitao², Hajime Takebe³ (1. INSS, 2. NEL, 3. KEPCO)

Oral presentation

[2O07-10] FP Behavior, FCVS

Thu. Sep 7, 2023 11:00 AM - 12:05 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Takafumi Narukawa(UTokyo)

11:00 AM - 11:15 AM

[2O07] A sensitivity analysis of the iodine production using a reaction kinetics dataset

*Giedre Zablackaite¹, Hiroyuki Shiotsu¹, Xiaoyu Zheng¹, Kentaro Kido¹ (1. JAEA)

11:15 AM - 11:30 AM

[2O08] Evaluation of FP Behavior Models in SAs

5. Evaluation of a chemical reaction model for Cs-I-B-H-O system in SA codes

*Hidetoshi Karasawa¹, Rizaal Muhammad¹, Shuhei Miwa¹, Chiaki Kino² (1. JAEA, 2. IAE)

11:30 AM - 11:45 AM

[2O09] Advanced Filtered Containment Venting System by Ionic Liquid

(4) Decomposition mechanism of ionic liquid mixed with water by gamma irradiation

*Sohei Fukui¹, Daiki Nunokawa¹, Kazuo Tominaga¹ (1. HGNE)

11:45 AM - 12:00 PM

[2O10] Study on FPs removal effect on the containment vessel penetrations during a severe accident

(3) Aerosol transport in parallel plate slit chnnels

*Akihiro KAKOI¹, Mizuki KOGA¹, Wei LIU¹, Koji MORITA¹, Koichi NAKAMURA², Taizo KANAI² (1. Kyushu Univ., 2. CRIEPI)

Time reserved for Chair （12:00 PM - 12:05 PM）

Oral presentation

[2O11-14] Advanced Reactor

Thu. Sep 7, 2023 2:45 PM - 3:50 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Ken-ichi Matsuba(JAEA)

2:45 PM - 3:00 PM

[2O11] Analytical Evaluation of loss of forced cooling tests using HTTR

*Sota Nagase¹, Kazuhiro Sawa¹, Satoru Nagasumi², Etsuo Ishitsuka², Kazuhiko Iigaki² (1. Hokkaido Univ., 2. JAEA)

3:00 PM - 3:15 PM

[2O12] Study on Diffusion Release of Cesium from Coated Fuel Particles for High Temperature Gas-cooled Reactors

*Masaki Yoshino¹, Kazuhiro Sawa¹, Jun Aihara² (1. Hokkaido Univ., 2. JAEA)

3:15 PM - 3:30 PM

[2O13] Proposal of Regulatory Guide for MSR Severe Accident

*Ritsuo Yoshioka¹, Yoichiro Shimazu², Takeshi Morita¹, Koji Ogasawara¹, Motoyasu Kinoshita¹, Masaaki Furukawa³ (1. International Thorium Molten-Salt Forum, 2. Beyond Energy Research & Development Association, 3. Thorium Tech Solution Inc.)

3:30 PM - 3:45 PM

[2O14] A study of tube inclination and jacket plate effect on freeze plug performance in molten salt reactors

*Ilham Muhammad¹, Tomio Okawa¹ (1. UEC)

Time reserved for Chair （3:45 PM - 3:50 PM）

Oral presentation

[2O15-18] Accident Behavior inside Building

Thu. Sep 7, 2023 3:50 PM - 4:55 PM Room O (School of Eng. Bildg. 2F 522)

Chair:Tomoaki SAKURAI(NRA)

3:50 PM - 4:05 PM

[2O15] Effect of hydrogen emissions from buildings during significant containment leaks in PWRs.

(1) Parameter study using simple model

*Kenichiro Ueda¹, Yasumitsu Fujii², Hidenori Kanaoka³, Kosuke Takeuchi⁴, Takahide Yoshida⁵, Wataru Urano⁶, Yasutaka Harai¹ (1. Mitsubishi Heavy Industries,Ltd., 2. The Kansai Electric Power Co, Inc., 3. Hokkaido Electric Power Co.,Inc., 4. Shikoku Electric Power Company, Incorporated, 5. KYUSHU ELECTRIC POWER CO., INC., 6. The Japan Atomic Power Company)

4:05 PM - 4:20 PM

[2O16] Effect of hydrogen emissions from buildings during significant containment leaks in PWRs.

(2) Hydrogen diffusion and mixing analysis with detailed annulus shape

*Yasutaka Harai¹, Ryo Fukuda¹, Kenichiro Ueda¹, Hiroyuki Sakamoto², Tomoya Iwamoto² (1. MHI, 2. MHI NSE)

4:20 PM - 4:35 PM

[2O17] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(1)Analysis of hydrogen concentration distribution in the reactor building during blowout panel operation

*Fumitomo Onishi¹, Achihiro Hamano¹, Toshiharu Mitsuhashi ¹, Atuso Takahashi¹, Hirotaka Hadachi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft)

4:35 PM - 4:50 PM

[2O18] Development of Reactor Building and Containment Vessel Thermo-Fluid Dynamics Code, Advance/BAROC

(2) Analysis for NSPP aerosol experiment

*Atsuo Takahashi¹, Toshiharu Mitsuhashi¹, Achihiro Hamano¹, Fumitomo Onishi¹, Hirotaka Hadachi¹, Hideaki Koike¹, Masanori Naitoh¹ (1. AdvanceSoft Corporation)

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

Oral presentation

[2O19-22] Aging Management

Thu. Sep 7, 2023 4:55 PM - 6:00 PM Room O (School of Eng. Bildg. 2F 522)

Chair:KOSUKE NAMBA(CRIEPI)

4:55 PM - 5:10 PM

[2O19] Radiation Effects on Concrete Structure for Aging management

(1)Overall Project Background and Research Outline

*Kiyoteru Suzuki¹, Masayuki Takizawa¹, Osamu Kontani², Ippei Maruyama³ (1. MRI, 2. KAJIMA, 3. UTokyo)

5:10 PM - 5:25 PM

[2O20] Radiation Effects on Concrete Structure for Aging management

(2)Evaluation of Irradiation Effects of RC Member by RBSM

*Daisuke Kambayashi¹, Shohei Sawada¹, Yosuke Kono¹, Kiyoteru Suzuki², Ippei Maruyama³ (1. KAJIMA, 2. MRI, 3. UTokyo)

5:25 PM - 5:40 PM

[2O21] Radiation Effects on Concrete Structure for Aging management

(3)Evaluation of Irradiation Effects of RC Member by FEM

*Yosuke Kono¹, Shohei Sawada¹, Kiyoteru Suzuki², Ippei Maruyama³ (1. KAJIMA, 2. MRI, 3. UTokyo)

5:40 PM - 5:55 PM

[2O22] Radiation Effects on Concrete Structure for Aging management

(4)Estimation of the Reference Values of Radiation Effects on Concrete Structure

*Masaki Kawai Kawai¹, Junji Etoh¹, Kiyoteru Suzuki¹, Kenta Murakami², Takahiro Ohkubo³, Shohei Sawada⁴, Ippei Maruyama² (1. MRI, 2. UTokyo, 3. Chiba Univ., 4. KAJIMA)

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

Sessions

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

[1O01-04] SFR 1

(32) Project Overview and Progress until 2022

(33) Corrosion behavior of B4C pellet immersed in molten stainless steel

(34) Ultra-high temperature thermal analysis of SUS316L containing 14, 17mass%B4C using blackbody radiation during melting and solidification

(35) Solidification process of SUS316L containing 14, 17mass%B4C by combination of in-situ observation and rapid cooling with electromagnetic levitation method

[1O05-08] SFR2

(11) Overview of project progress

(12) Measurement of thermophysical properties and evaluation of salt-based fuels

(13) Evaluations on core performance with candidate device specifications

(14) Evaluations on non-proliferation features of the passive shutdown device

[1O09-12] SFR 3

(11) Coolability of molten fuel discharged into a depth- and volume-limited sodium plenum

[1O13-14] Estimation of Fukushima Daiichi Accident

[1O15-20] Floating Reactor

(1)Overview of the development at COCN

(2)Results of COCN study on nuclear security

(3)Vital area identification and path analysis on nuclear security

(4) Preliminary estimation of passive cooling system for OFNP

(5)Void behavior of forced convection boiling under flow and power oscillation assuming offshore swinging

(6) Assessment of consequences of heaving of offshore floating nuclear power on accident progression

[2O01-06] Accident Behavior, Emergency Exercise

(2) Study of oxidation model for Cu vapor

[2O07-10] FP Behavior, FCVS

5. Evaluation of a chemical reaction model for Cs-I-B-H-O system in SA codes

(4) Decomposition mechanism of ionic liquid mixed with water by gamma irradiation

(3) Aerosol transport in parallel plate slit chnnels

[2O11-14] Advanced Reactor

[2O15-18] Accident Behavior inside Building

(1) Parameter study using simple model

(2) Hydrogen diffusion and mixing analysis with detailed annulus shape

(1)Analysis of hydrogen concentration distribution in the reactor building during blowout panel operation

(2) Analysis for NSPP aerosol experiment

[2O19-22] Aging Management

(1)Overall Project Background and Research Outline

(2)Evaluation of Irradiation Effects of RC Member by RBSM

(3)Evaluation of Irradiation Effects of RC Member by FEM

(4)Estimation of the Reference Values of Radiation Effects on Concrete Structure

Authentication

(33) Corrosion behavior of B₄C pellet immersed in molten stainless steel

(34) Ultra-high temperature thermal analysis of SUS316L containing 14, 17mass%B₄C using blackbody radiation during melting and solidification

(35) Solidification process of SUS316L containing 14, 17mass%B₄C by combination of in-situ observation and rapid cooling with electromagnetic levitation method