Oral presentation

[2K07-13] Resilience of Nuclear Structures

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

chair: Shigeki Okamura (Toyama Prefectural Univ.)

2:45 PM - 3:00 PM

[2K07] Development of failure mitigation technologies for improving resilience of nuclear structures

(5)Proposal of failure mitigatgion method by fracture control

*Naoto Kasahara¹, Hidemasa Yamano², Izumi Nakamura³, Kazuyuki Demachi¹, Takuya Sato¹, Masakazu Ichimiya¹ (1. The University of Tokyo, 2. JAEA, 3. NIED)

3:00 PM - 3:15 PM

[2K08] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(6)How to consider the effects of fracture control into resilience index

*Kazuyuki Demachi¹, Yuto Kuwabara¹, Shi Chen¹, Naoto Kasahara¹, Hiroyuki Nishino², Yuichi Onoda², Kenichi Kurisaka² (1. UTokyo, 2. JAEA)

3:15 PM - 3:30 PM

[2K09] Development of failure mitigation technologies for improving resilience of nuclear structures

(7)Effectiveness evaluation technology of the measures for improving resilience at ultra-high temperatures

*Yuichi Onoda¹, Hiroyuki Nishino¹, Kenichi Kurisaka¹, Hidemasa Yamano¹, Kazuyuki Demachi² (1. JAEA, 2. UTokyo)

3:30 PM - 3:45 PM

[2K10] Development of failure mitigation technologies for improving resilience of nuclear structures

(8)Effectiveness evaluation technology of the measures for improving resilience against excessive earthquake

*Hiroyuki Nishino¹, Yuichi Onoda¹, Kenichi Kurisaka¹, Hidemasa Yamano¹, Kazuyuki Demachi² (1. JAEA, 2. UTokyo)

3:45 PM - 4:00 PM

[2K11] Development of failure mitigation technologies for improving resilience of nuclear structures

(9)Fundamental study on post-buckling behavior under excessive seismic load

*Sho Hasegawa¹, Masakazu Ichimiya¹, Naoto Kasahara¹ (1. UTokyo)

4:00 PM - 4:15 PM

[2K12] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(10)Research plan for failure sequence control under excessive earthquakes

*Izumi Nakamura¹, Naoto Kasahara² (1. NIED, 2. UTokyo)

4:15 PM - 4:30 PM

[2K13] Development of failure mitigation technologies for improving resilience of nuclear structures

(11)Analysis for enhancing resilience of next-generation nuclear power plants

*Satoshi Futagami¹, Masanori Ando¹, Hidemasa Yamano¹ (1. JAEA)

Time reserved for Chair （4:30 PM - 4:45 PM）

Oral presentation

[2K14-17] Small Sodium-cooled Fast Reactor

Thu. Sep 9, 2021 4:45 PM - 6:00 PM Room K

chair: Yuichi Onoda (JAEA)

4:45 PM - 5:00 PM

[2K14] Development of an innovative small sodium-cooled fast reactor

(6)Transition scenario to fast reactor equilibrium cycle

*Daisuke Watanabe¹, Keita Endo¹, Hirotaka Nakahara¹, Kazuhiko Matsumura¹, Masatoshi Iizuka² (1. Hitachi-GE, 2. CRIEPI)

5:00 PM - 5:15 PM

[2K15] Development of an innovative small sodium-cooled fast reactor

(7)Pyroprocessing and metal fuel fabrication during transitional and equilibrium period of fast reactor cycle

*Masatoshi Iizuka¹, Kensuke Kinoshita¹, Daisuke Watanabe², Hirotaka Nakahara² (1. CRIEPI, 2. HItath-GE)

5:15 PM - 5:30 PM

[2K16] Development of an innovative small sodium-cooled fast reactor

(8)Core concept of sodium-cooled fast reactor for domestic deployment with multi-recycled metal fuel

*Sho Fuchita¹, Koji Fujimura¹, Keita Endo¹, Kazuhiro Fujimata¹, Daisuke Watanabe¹, Hirotaka Nakahara¹ (1. HGNE)

5:30 PM - 5:45 PM

[2K17] Development of an innovative small sodium-cooled fast reactor

(9)3D thermal hydraulic sensitivity analysis of RVACS heat removal characteristics

*Takashi Abe¹, Kazuhiro Fujimata¹, Hirotaka Nakahara¹, Kazuhiko Matsumura¹ (1. HGNE)

Time reserved for Chair （5:45 PM - 6:00 PM）

Oral presentation

[3K01-06] Fast reactor equipment

Fri. Sep 10, 2021 9:30 AM - 11:10 AM Room K

chair: Tomomi Otani (MFBR)

9:30 AM - 9:45 AM

[3K01] A Study on Structures of Reactor Vessel of Pool-type Sodium-cooled Fast Reactor in case of adopted Three-dimensional seismic isolation system

*Masato Uchita¹, Takayuki Miyagawa¹, Hisatomo Murakami², Tetsuji Suzuno², Tomohiko Yamamoto³ (1. JAPC, 2. MFBR, 3. JAEA)

9:45 AM - 10:00 AM

[3K02] Improvement of Signal Strength on Primary Heat Transport System Flow Rate in Pool type SFR

*Kazuya Takano¹, Atsushi Kato¹, Masato Uchita², Hitoshi Okazaki³, Risako Ikari³ (1. JAEA, 2. JAPC, 3. MFBR)

10:00 AM - 10:15 AM

[3K03] Study on Performance Evaluation of Self-actuated Shutdown System for Sodium-cooled Fast Reactor

Measurement of Flow Field around Temperature Sensing Part

*Tomoyuki Hiyama¹, Kosuke Aizawa¹, Jun Kobayashi¹, Akikazu Kurihara¹, Kazuyoshi Nagasawa², Hideyoshi Onuma³ (1. JAEA, 2. NESI, 3. Ascend)

10:15 AM - 10:30 AM

[3K04] Study on reflection of operating experience of Prototype Fast Breeder Reactor Monju fuel handling system to the next generation FBR

*Masafumi Rekimoto¹, Masato Ando¹, Yoshitaka Chikazawa¹, Tomoharu Hamano¹, Yasutaka Shiohama¹, Takayuki Miyagawa², Hiroyuki Hara³, Yamauchi Kanau³, Akihiro Ide⁴, Kenichi Tanabe⁵ (1. JAEA, 2. JAPC, 3. MFBR, 4. MHI, 5. Fuji Electric)

10:30 AM - 10:45 AM

[3K05] Development of Failure Probability Evaluation Method with Integrated Energy for Seismic PRA in Fast Reactor

(1)Development Plan of Evaluation Method

*Shigeki Okamura¹, Takahiro Kinoshita¹, Hiroyuki Nishino², Hidemasa Yamano², Kenichi Kurisaka², Satoshi Futagami², Tsuyoshi Fukasawa³ (1. Toyama Prefectural Univ., 2. JAEA, 3. TDU)

10:45 AM - 11:00 AM

[3K06] Development of Failure Probability Evaluation Method with Integrated Energy for Seismic PRA in Fast Reactor

(2)Estimation of Integrated Energy based on Fatigue Test of Material

*Takahiro Kinoshita¹, Shigeki Okamura¹, Hiroyuki Nishino², Hidemasa Yamano², Kenichi Kurisaka², Satoshi Futagami², Tsuyoshi Fukasawa³ (1. Toyama Prefectural Univ., 2. JAEA, 3. TDU)

Time reserved for Chair （11:00 AM - 11:10 AM）

Oral presentation

[3K07-09] Fast Reactor Core & Fuel 1

Fri. Sep 10, 2021 11:10 AM - 12:00 PM Room K

chair: Toru Obara (Tokyo Tech)

11:10 AM - 11:25 AM

[3K07] Characterization of BN particle dispersion SiC composites for GFR in SafeG project

*Tatsuya Hinoki¹, Branislav Hatala², Zoltán Hózer³ (1. Kyoto University, 2. VUJE, Inc., 3. Centre for Energy Research)

11:25 AM - 11:40 AM

[3K08] Neutronics benchmark analysis of FFTF loss of flow without scram test No.13

*Kazuya Ohgama¹, Atsushi Takegoshi², Erina Hamase¹, Norihiro Doda¹, Hidemasa Yamano¹, Masaaki Tanaka¹ (1. JAEA, 2. NESI)

11:40 AM - 11:55 AM

[3K09] Development of transient behavior analysis code for metal fuel fast reactor during initiating phase of core disruptive accident

(1)Code modification based on experimental analysis of transient overpower tests

*Hirokazu Ohta¹, Kouji Kusumi¹, Hidemasa Yamano², Kazuya Ohgama², Satoshi Futagami², Sadae Shimada³, Yumi Yamada³ (1. CRIEPI, 2. JAEA, 3. MFBR)

Time reserved for Chair （11:55 AM - 12:00 PM）

Oral presentation

[3K10-13] Fast Reactor Core & Fuel 2

Fri. Sep 10, 2021 2:45 PM - 3:55 PM Room K

chair: Hirokazu Ohta (CRIEPI)

2:45 PM - 3:00 PM

[3K10] Study on Optimization for reducing Sodium Void Reactivity in Sodium-cooled Fast Reactor

(1)Design of Fuel Composition using a Global Optimization Method

*Hiroya Oike¹, Masaki Morishita¹, Tomohiro Endo¹, Akio Yamamoto¹, Go Chiba² (1. Nagoya Univ., 2. Hokkaido Univ.)

3:00 PM - 3:15 PM

[3K11] Study on Optimization for reducing Sodium Void Reactivity in Sodium-cooled Fast Reactor

(2)Automated search of core geometry

*Yuki Morishita¹, Hiroya Oike¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya Univ.)

3:15 PM - 3:30 PM

[3K12] Evaluation of the impact of TRU composition on the core characteristics of fast reactors during the transition period

*Hiroki Kato¹, Go Chiba¹ (1. Hokkaido Univ.)

3:30 PM - 3:45 PM

[3K13] Conceptual design of rotational fuel shuffling sodium cooled Breed-and-Burn fast reactor

*Toru Obara¹, Van Khanh Hoang², Odmaa Sambuu³, Jun Nishiyama¹ (1. Tokyo Tech, 2. VinAtom, 3. NUM)

Time reserved for Chair （3:45 PM - 3:55 PM）

Oral presentation

[3K14-17] High Temperature Gas Reactor

Fri. Sep 10, 2021 3:55 PM - 5:05 PM Room K

chair: Kazuya Takano (JAEA)

3:55 PM - 4:10 PM

[3K14] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part2

(2)Study of the cogeneration HTGR's system design

*Hiroki Tsukamoto¹, Syoichi Horii¹, Taro Kato¹ (1. Mitsubishi Heavy Industries, Ltd. )

4:10 PM - 4:25 PM

[3K15] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part2

(3)Conceptual examination of plant control

*Hokuto Tsuruoka¹, Masaaki Katayama¹, Wataru Sakuma¹ (1. Reactor Safety System Engineering Section, Reactor Core & Safety Department ,Nuclear Energy Systems, MHI)

4:25 PM - 4:40 PM

[3K16] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part2

(4)Approach to Safety and Selection of Safety Analysis Events

*Takafumi Ikeda¹, Wataru Sakuma¹ (1. MHI)

4:40 PM - 4:55 PM

[3K17] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part2

(5)Feasibility Design Study of Main Components

*Shin Kusuda¹, Hiroto Tanishima¹, Mitsuru Nakamura¹, Takaya Kusakabe¹ (1. MHI)

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

Sessions

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[2K07-13] Resilience of Nuclear Structures

(5)Proposal of failure mitigatgion method by fracture control

(6)How to consider the effects of fracture control into resilience index

(7)Effectiveness evaluation technology of the measures for improving resilience at ultra-high temperatures

(8)Effectiveness evaluation technology of the measures for improving resilience against excessive earthquake

(9)Fundamental study on post-buckling behavior under excessive seismic load

(10)Research plan for failure sequence control under excessive earthquakes

(11)Analysis for enhancing resilience of next-generation nuclear power plants

[2K14-17] Small Sodium-cooled Fast Reactor

(6)Transition scenario to fast reactor equilibrium cycle

(7)Pyroprocessing and metal fuel fabrication during transitional and equilibrium period of fast reactor cycle

(8)Core concept of sodium-cooled fast reactor for domestic deployment with multi-recycled metal fuel

(9)3D thermal hydraulic sensitivity analysis of RVACS heat removal characteristics

[3K01-06] Fast reactor equipment

Measurement of Flow Field around Temperature Sensing Part

(1)Development Plan of Evaluation Method

(2)Estimation of Integrated Energy based on Fatigue Test of Material

[3K07-09] Fast Reactor Core & Fuel 1

(1)Code modification based on experimental analysis of transient overpower tests

[3K10-13] Fast Reactor Core & Fuel 2

(1)Design of Fuel Composition using a Global Optimization Method

(2)Automated search of core geometry

[3K14-17] High Temperature Gas Reactor

(2)Study of the cogeneration HTGR's system design

(3)Conceptual examination of plant control

(4)Approach to Safety and Selection of Safety Analysis Events

(5)Feasibility Design Study of Main Components

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