Oral presentation

[1C01-04] High Temoerature Gas Reactor

Wed. Mar 16, 2022 9:30 AM - 10:45 AM Room C

Chair: Masaaki Tanaka (JAEA)

9:30 AM - 9:45 AM

[1C01] HTTR Heat Application Test Project

(1)Summary of Test Project

*Hiroyuki Sato¹, Takeshi Aoki¹, Shoichiro Okita¹, Hasegawa Takeshi¹, Atsushi Shimizu¹, Kazuhiko Iigaki¹, Nariaki Sakaba¹ (1. Japan Atomic Energy Agency)

9:45 AM - 10:00 AM

[1C02] HTTR Heat Application Test Project

(2)Development of Plant Dynamics Evaluation Methodology

*Takeshi Aoki¹, Hiroyuki Sato¹, Nariaki Sakaba¹ (1. JAEA)

10:00 AM - 10:15 AM

[1C03] HTTR Heat Application Test Project

(3)Development of Combustible Gas Fire and Explosion Effect Evaluation Methodology

*Takeshi Hasegawa¹, Takeshi Aoki¹, Hiroyuki Sato¹, Nariaki Sakaba¹ (1. JAEA)

10:15 AM - 10:30 AM

[1C04] Development of AL-DENTE (AnaLysis tool system for Dose EvaluatioN in accidents of high TEmperature gas-cooled reactors)

*Shoichiro Okita¹, Takeshi Aoki¹, Hiroyuki Sato¹, jun Aihara¹, Hirofumi Ohashi¹ (1. Japan Atomic Energy Agency)

Time reserved for Chair （10:30 AM - 10:45 AM）

Oral presentation

[1C05-08] AI Technology

Wed. Mar 16, 2022 10:45 AM - 12:00 PM Room C

Chair: Shuhei Maruyama (JAEA)

10:45 AM - 11:00 AM

[1C05] Applicability Study of Bayesian Optimization in Core Neutronic Design

*Kazuki Kuwagaki¹, Kenji Yokoyama¹ (1. JAEA)

11:00 AM - 11:15 AM

[1C06] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(5)Investigation of optimization processes in design optimization support tool, ARKADIA-Design

*Masaaki Tanaka¹, Norihiro Doda¹, Kenji Yokoyama¹, Takero Mori¹, Satoshi Okajima¹, Ryuta Hashidate¹, Hiroki Yada¹, Shigeo Ohki¹, Masashi Miyazaki¹, Shigeru Takaya¹ (1. JAEA)

11:15 AM - 11:30 AM

[1C07] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(6)Development of ex-vessel analysis model in ARKADIA-Safety for safety evaluation

*Akihiro Uchibori¹, Mitsuhiro Aoyagi¹, Masateru Sonehara¹, Joji Sogabe¹, Yasushi Okano¹, Takashi Takata² (1. JAEA, 2. UTokyo)

11:30 AM - 11:45 AM

[1C08] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(7)Development of knowledge base system for fast reactor system design

*Yasuhiro Enuma¹, Yuki Kondo¹, Ryuta Hashidate¹, Rika Mitsumoto¹, Taira Hazama¹, Kazuyuki Demachi² (1. JAEA, 2. UTokyo)

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

Oral presentation

[1C09-12] Fast Reactor

Wed. Mar 16, 2022 2:45 PM - 4:00 PM Room C

Chair: Taro Kan (MFBR)

2:45 PM - 3:00 PM

[1C09] Study on Optimization for reducing Sodium Void Reactivity in Sodium-cooled Fast Reactor

(3)Design of Fuel Composition Containing Light and Medium Nuclides

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

3:00 PM - 3:15 PM

[1C10] Evaluation of the impact of TRU composition on the core characteristics of fast reactors during the transition period

(2)Core characteristics of the FR in the transition period with high-burnup LWR spent fuel

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

3:15 PM - 3:30 PM

[1C11] Development of equilibrium cycle refueling pattern optimization tool in sodium-cooled fast reactor core design

*Shuhei Maruyama¹, Kenji Yokoyama¹, Shigeo Ohki¹ (1. Japan Atomic Energy Agency)

3:30 PM - 3:45 PM

[1C12] Study on Performance Evaluation of Self-actuated Shutdown System for Sodium-cooled Fast Reactor

Evaluation on Flow Field around Temperature Sensing Part

*Kosuke Aizawa¹, Tomoyuki Hiyama¹, Jun kobayashi¹, Akikazu Kurihara¹ (1. JAEA)

Time reserved for Chair （3:45 PM - 4:00 PM）

Oral presentation

[1C13-17] Next Generation Reactor Safety

Wed. Mar 16, 2022 4:00 PM - 5:30 PM Room C

Chair: Akihiro Uchibori (JAEA)

4:00 PM - 4:15 PM

[1C13] Possibility of thorium utilization by molten salt fast reactor having characteristics of fuel self-sufficiency

*Koshi Mitachi¹ (1. Beyond Energy Research & Development Association)

4:15 PM - 4:30 PM

[1C14] Manufacturing of fluoride molten salt loop and performance test (2)

*Motoyasu Kinoshita^1,3, Aji Indarta², Kaito Kubo², Kouichi Yageta³, Fumihiro Chiba³, Tatsumi Arima², Kazunari Katayama², Satoshi Fukada¹ (1. MOSTECH Co., 2. Kyusyu Univ., 3. MSLab inc.)

4:30 PM - 4:45 PM

[1C15] Development of failure mitigation technologies for improving resilience of nuclear structures

(12)Study of buckling and post-buckling of vessels for failure mitigation at extremely high temperature

*Naoto Kasahara¹, Masato Murohara¹, Takuya Sato¹ (1. UTokyo)

4:45 PM - 5:00 PM

[1C16] Development of failure mitigation technologies for improving resilience of nuclear structures

(13)Study on buckling and post-buckling behavior of beams for failure consequence mitigation under excessive seismic loads

*Ryota Hamada¹, Sho Hasegawa¹, Masakazu Ichimiya¹, Naoto Kasahara¹ (1. UTokyo)

5:00 PM - 5:15 PM

[1C17] Development of failure mitigation technologies for improving resilience of nuclear structures

(14)PRA Analysis Method for Visualizing the Effect of Resilience Improvement Considering Time Effect and Dynamic Change of Events

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

Time reserved for Chair （5:15 PM - 5:30 PM）

Sessions

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

[1C01-04] High Temoerature Gas Reactor

[1C01] HTTR Heat Application Test Project

(1)Summary of Test Project

[1C02] HTTR Heat Application Test Project

(2)Development of Plant Dynamics Evaluation Methodology

[1C03] HTTR Heat Application Test Project

(3)Development of Combustible Gas Fire and Explosion Effect Evaluation Methodology

[1C04] Development of AL-DENTE (AnaLysis tool system for Dose EvaluatioN in accidents of high TEmperature gas-cooled reactors)

[1C05-08] AI Technology

[1C05] Applicability Study of Bayesian Optimization in Core Neutronic Design

[1C06] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(5)Investigation of optimization processes in design optimization support tool, ARKADIA-Design

[1C07] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(6)Development of ex-vessel analysis model in ARKADIA-Safety for safety evaluation

[1C08] Development of Advanced Reactor Knowledge- and AI-aided Design Integration Approach through the whole plant lifecycle, ARKADIA

(7)Development of knowledge base system for fast reactor system design

[1C09-12] Fast Reactor

[1C09] Study on Optimization for reducing Sodium Void Reactivity in Sodium-cooled Fast Reactor

(3)Design of Fuel Composition Containing Light and Medium Nuclides

[1C10] Evaluation of the impact of TRU composition on the core characteristics of fast reactors during the transition period

(2)Core characteristics of the FR in the transition period with high-burnup LWR spent fuel

[1C11] Development of equilibrium cycle refueling pattern optimization tool in sodium-cooled fast reactor core design

[1C12] Study on Performance Evaluation of Self-actuated Shutdown System for Sodium-cooled Fast Reactor

Evaluation on Flow Field around Temperature Sensing Part

[1C13-17] Next Generation Reactor Safety

[1C13] Possibility of thorium utilization by molten salt fast reactor having characteristics of fuel self-sufficiency

[1C14] Manufacturing of fluoride molten salt loop and performance test (2)

[1C15] Development of failure mitigation technologies for improving resilience of nuclear structures

(12)Study of buckling and post-buckling of vessels for failure mitigation at extremely high temperature

[1C16] Development of failure mitigation technologies for improving resilience of nuclear structures

(13)Study on buckling and post-buckling behavior of beams for failure consequence mitigation under excessive seismic loads

[1C17] Development of failure mitigation technologies for improving resilience of nuclear structures

(14)PRA Analysis Method for Visualizing the Effect of Resilience Improvement Considering Time Effect and Dynamic Change of Events

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