Oral presentation

[1H01-07] Resilience of Nuclear Structures

Wed. Sep 6, 2023 10:00 AM - 11:55 AM Room H (ES Bildg. 2F ES022)

Chair:Tadakatsu Yodo(MHI)

10:00 AM - 10:15 AM

[1H01] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(23)Fundamental study on passive safety of piping systems under earthquake

*Riku Horinouchi¹, Masakazu Ichimiya¹, Naoto Kasahara¹ (1. UTokyo)

10:15 AM - 10:30 AM

[1H02] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(24) Examination of seismic passive-safety of small-bore hole piping system with multiple support structure

*Izumi Nakamura¹, Naoto Kasahara² (1. National Research Institute for Earth Science and Disaster Resilience, 2. The University of Tokyo)

10:30 AM - 10:45 AM

[1H03] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(25) Fundamental study on passive cooling by radiation and natural convection

Maxence Laraison², Kensuke Narumi¹, Takuya Sato¹, *Naoto Kasahara¹ (1. The University of Tokyo, 2. Ecole Polytechnique, France)

10:45 AM - 11:00 AM

[1H04] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(26) Preliminary Evaluation for Effectiveness of the Measures for Improving Resilience at Ultra-High Temperatures

*Yuichi Onoda¹, kenichi Kurisaka¹, Hidemasa Yamano¹ (1. Japan Atomic Energy Agency)

11:00 AM - 11:15 AM

[1H05] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(27) Preliminary Evaluation for Effectiveness of the Measures for Improving Resilience against Excessive Earthquake

*Hiroyuki Nishino¹, Kenichi Kurisaka¹, Hidemasa Yamano¹ (1. Japan Atomic Energy Agency)

11:15 AM - 11:30 AM

[1H06] Development of Failure Mitigation Technologies for Improving Resilience of Nuclear Structures

(28)Passive Safety Structure for Improving Resilience of Next-Generation Nuclear Power Plants under Extremely High Temperature Conditions

*Satoshi FUTAGAMI¹, Masanori ANDO¹, Hidemasa YAMANO¹, Naoto KASAHARA² (1. JAEA, 2. UTokyo)

11:30 AM - 11:45 AM

[1H07] Development of failure mitigation technologies for improving resilience of nuclear structures

(29)Visualization of resilience improvement through passive safety structure using resilience index

*Satoshi Abe¹, Kazuyuki Demachi¹, Shi Chen¹, Naoto Kasahara¹ (1. UTokyo)

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

Oral presentation

[1H08-12] Small Sodium-cooled Fast Reactor

Wed. Sep 6, 2023 2:45 PM - 4:10 PM Room H (ES Bildg. 2F ES022)

Chair:Yuichi Onoda(JAEA)

2:45 PM - 3:00 PM

[1H08] Development of an innovative small sodium-cooled fast reactor

(13) Multi-recycle of metal fuel in MA transmutation scenario

*Daisuke Watanabe¹, Keita Endo¹, Sho Fuchita¹, Koji Fujimura¹, Hirotaka Nakahara¹, Kensuke Kinoshita² (1. Hitachi-GE, 2. CRIEPI)

3:00 PM - 3:15 PM

[1H09] Development of an innovative small sodium-cooled fast reactor

(14) Safety improvement study of the metal fuel fast reactor core for domestic deployment

*Sho Fuchita¹, Koji Fujimura¹, Kazuhiro Fujimata¹, Hirotaka Nakahara¹, Hirokazu Ohta² (1. Hitachi GE, 2. CRIEPI)

3:15 PM - 3:30 PM

[1H10] Development of an innovative small sodium-cooled fast reactor

(15) Irradiation behavior analyses of metal fuel elements based on core design

*Hirokazu Ohta¹, Sho Fuchita², Koji Fujimura ², Hirotaka Nakahara ² (1. CRIEPI, 2. Hitachi-GE)

3:30 PM - 3:45 PM

[1H11] Development of an innovative small sodium-cooled fast reactor

(16) Derivation of expansion reactivity based on reactivity coefficient and detailed transient analysis

*Satoshi Takeda¹, Takanori Kitada¹, Hisaya Endo¹, Koji Fujimura², Sho Fuchita² (1. Osaka University, 2. Hitachi-GE Nuclear Energy, Ltd.)

3:45 PM - 4:00 PM

[1H12] Development of an innovative small sodium-cooled fast reactor

(17) 3D thermal hydraulic transient analysis of RVACS heat removal characteristics (part 2)

*Keita Endo¹, Takashi Abe¹, Kazuhiro Fujimata¹, Hirotaka Nakahara¹ (1. Hitachi-GE)

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

Oral presentation

[1H13-17] Innovative Reactor

Wed. Sep 6, 2023 4:10 PM - 5:35 PM Room H (ES Bildg. 2F ES022)

Chair:Hirokazu Ohta(CRIEPI)

4:10 PM - 4:25 PM

[1H13] Feasibility of a small RFBB concept with lead coolant and nitride fuel

*Alexandru Catalin Stafie¹, Jun Nishiyama², Toru Obara¹ (1. Tokyo Tech, 2. TCU)

4:25 PM - 4:40 PM

[1H14] Small sodium-cooled RFBB with nitride fuel and LBE Reflectors

*Tsendsuren Amarjargal¹, Jun Nishiyama², Toru Obara¹ (1. Tokyo Institute of Technology, 2. Tokyo City University)

4:40 PM - 4:55 PM

[1H15] Development of Mitsubishi multi-purpose modular ultra-safety micro reactor

(4) Selection of accident sequence

*Tadakatsu Yodo¹, Shohei Otsuki¹, Hideki Miwa¹, Shinsuke Nakano¹, Satoru Kamohara¹ (1. MHI)

4:55 PM - 5:10 PM

[1H16] Neutronics - thermal hydraulics behavior of inclined offshore floating BWR

*Kodai Fukuda¹, Kenya Suyama¹, Toru Obara² (1. JAEA, 2. Tokyo Tech)

5:10 PM - 5:25 PM

[1H17] Impact resistance evaluation for CDA in a pool type reactor with common specifications

*Masao Eto¹, Shinobu Yokoi¹, Tomoyuki Inoue¹, Masato Yamashita², Kazuhiro Miura², Takashi Okafuji², Yuichi Onoda³, Tomohiko Yamamoto³, Masato Uchita⁴ (1. MFBR, 2. MHI, 3. JAEA, 4. JAPC)

Time reserved for Chair （5:25 PM - 5:35 PM）

Oral presentation

[2H01-05] Molten Salt Reactor 1

Thu. Sep 7, 2023 9:30 AM - 10:55 AM Room H (ES Bildg. 2F ES022)

Chair:Motoyasu Kinoshita(Kyushu Univ.)

9:30 AM - 9:45 AM

[2H01] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(1) Outline of the study

*Michio Yamawaki¹, Hiroyasu Mochizuki², Yoshihisa Tahara², Koshi Mitachi¹, Yoichiro Shimazu¹, Yuji Arita³, Tadafumi Koyama⁴, Tsuyoshi Murakami⁴, Ken-ichi Fukumoto³, Takuya Goto⁵ (1. Beyond Energy R&D Association, 2. Tokyo Tech, 3. U. Fukui, 4. CRIEPI, 5. Doshisha U.)

9:45 AM - 10:00 AM

[2H02] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(2) Safety in the event of transients

*Hiroyasu MOCHIZUKI¹ (1. Tokyo Tech)

10:00 AM - 10:15 AM

[2H03] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(3) Criticality analysis

*Yoshihisa Tahara^1,2, Satoshi Chiba^1,3 (1. Tokyo Tech, 2. NAIS, 3. NAT)

10:15 AM - 10:30 AM

[2H04] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(4) Burn-up characteristics of a small molten-salt fast reactor

*Koshi Mitachi¹, Yoichiro Shimazu¹ (1. Beyond Energy Research & Development Association)

10:30 AM - 10:45 AM

[2H05] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(5) Viscosity of chloride salt fuel

*Koki HAGIHARA¹, Yuji ARITA¹, Kyoya YAMASHITA¹ (1. Univ. Fukui)

Time reserved for Chair （10:45 AM - 10:55 AM）

Oral presentation

[2H06-09] Molten Salt Reactor 2

Thu. Sep 7, 2023 10:55 AM - 12:00 PM Room H (ES Bildg. 2F ES022)

Chair:Ren Shimada(MFBR)

10:55 AM - 11:10 AM

[2H06] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(6)Electrochemical property measurements of molten chloride salt to construct reprocessing process

*Tsuyoshi Murakami¹, Tadafumi Koyama¹ (1. CRIEPI)

11:10 AM - 11:25 AM

[2H07] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(7) Research about compatibility under ion irradiation on Ni-based alloy with chloride salt

*Daiki Takebayashi¹, Ken-ichi Fukumoto¹ (1. Univ. of Fukui)

11:25 AM - 11:40 AM

[2H08] Feasibility Study of Integral Molten Chloride Salt Fast Reactor (III)

(8) Corrosion behavior of Ni-based alloys in molten chloride containing La and Ce

*Takashi Watanabe¹, Takuya Goto¹, Yuta Suzuki¹ (1. Doshisha Univ.)

11:40 AM - 11:55 AM

[2H09] Why Moten Salt Reactor has not been deployed yet?

- technological issues mainly -

*Motoyasu KINOSHITA Kinoshita¹ (1. Kyushu Univ.)

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

Oral presentation

[2H10-12] High Temperature Gas Reactor

Thu. Sep 7, 2023 2:45 PM - 3:35 PM Room H (ES Bildg. 2F ES022)

Chair:Kosuke Aizawa(JAEA)

2:45 PM - 3:00 PM

[2H10] Study of two-dimensional heat transfer analysis model of HTTR vessel cooling system

*HARUKI HASHIMOTO¹, Kazuhiro Sawa¹, Tomonari Hasegawa², Satoru Nagasumi², Etsuo Ishitsuka², Kazuhiko Iigaki² (1. Hokkaido Univ., 2. JAEA)

3:00 PM - 3:15 PM

[2H11] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part4

(1) Study of Core Design

*Atsuko Kubo¹, Yusuke Sato¹, Kazuya Yamaji¹, Koji Asano¹, Takahiro Shimizu¹, Ichiyo Matoba¹, Takayuki Nakano¹, Kazumasa Suyama¹ (1. MHI)

3:15 PM - 3:30 PM

[2H12] Development of High Temperature Gas Reactor Cogeneration Plant without Core Melting Part4

(2) Study of Safety Analysis

*Masaaki Katayama¹, Sakuma Wataru¹, Kazumasa Suyama¹ (1. Mitsubishi Heavy Industries, Ltd.)

Time reserved for Chair （3:30 PM - 3:35 PM）

Oral presentation

[2H13-15] Self-actuated Shutdown System

Thu. Sep 7, 2023 3:35 PM - 4:30 PM Room H (ES Bildg. 2F ES022)

Chair:Kazuya Yamaji(MHI)

3:35 PM - 3:50 PM

[2H13] Study on performance evaluation of Self-Actuated Shutdown System (SASS) in sodium-cooled fast reactor

(1)Project overview

*Kosuke Aizawa¹, Hidemasa Yamano¹, Shoko Matsunaga², Hironori Nakamura³, Ren Shimada³, Masato Aizawa Uchita⁴ (1. JAEA, 2. MHI, 3. MFBR, 4. JAPC)

3:50 PM - 4:05 PM

[2H14] Study on performance evaluation of Self-Actuated Shutdown System (SASS) in sodium-cooled fast reactor

(2) Flow field measurement around a temperature sensing alloy

*Ryota Yamasaki¹, Kosuke Aizawa¹, Jun Kobayashi¹, Akikazu Kurihara¹ (1. JAEA)

4:05 PM - 4:20 PM

[2H15] Study on performance evaluation of Self-Actuated Shutdown System (SASS) in sodium-cooled fast reactor

(3)Demonstration test of SASS in sodium

*Ren Shimada¹, Masatoshi Kameyama², Satoshi Futagami³, Shoko Matsunaga⁴, Fumito Kajitani⁴, Yoshihiko Yoshida⁴, Taisuke Inuzuka⁴, Keisuke Yoshida⁴ (1. Mitsubishi FBR Systems, Inc., 2. The Japan Atomic Power Company, 3. Japan Atomic Energy Agency, 4. Mitsubishi Heavy Industries)

Time reserved for Chair （4:20 PM - 4:30 PM）

Sessions

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

[1H01-07] Resilience of Nuclear Structures

(23)Fundamental study on passive safety of piping systems under earthquake

(24) Examination of seismic passive-safety of small-bore hole piping system with multiple support structure

(25) Fundamental study on passive cooling by radiation and natural convection

(26) Preliminary Evaluation for Effectiveness of the Measures for Improving Resilience at Ultra-High Temperatures

(27) Preliminary Evaluation for Effectiveness of the Measures for Improving Resilience against Excessive Earthquake

(28)Passive Safety Structure for Improving Resilience of Next-Generation Nuclear Power Plants under Extremely High Temperature Conditions

(29)Visualization of resilience improvement through passive safety structure using resilience index

[1H08-12] Small Sodium-cooled Fast Reactor

(13) Multi-recycle of metal fuel in MA transmutation scenario

(14) Safety improvement study of the metal fuel fast reactor core for domestic deployment

(15) Irradiation behavior analyses of metal fuel elements based on core design

(16) Derivation of expansion reactivity based on reactivity coefficient and detailed transient analysis

(17) 3D thermal hydraulic transient analysis of RVACS heat removal characteristics (part 2)

[1H13-17] Innovative Reactor

(4) Selection of accident sequence

[2H01-05] Molten Salt Reactor 1

(1) Outline of the study

(2) Safety in the event of transients

(3) Criticality analysis

(4) Burn-up characteristics of a small molten-salt fast reactor

(5) Viscosity of chloride salt fuel

[2H06-09] Molten Salt Reactor 2

(6)Electrochemical property measurements of molten chloride salt to construct reprocessing process

(7) Research about compatibility under ion irradiation on Ni-based alloy with chloride salt

(8) Corrosion behavior of Ni-based alloys in molten chloride containing La and Ce

- technological issues mainly -

[2H10-12] High Temperature Gas Reactor

(1) Study of Core Design

(2) Study of Safety Analysis

[2H13-15] Self-actuated Shutdown System

(1)Project overview

(2) Flow field measurement around a temperature sensing alloy

(3)Demonstration test of SASS in sodium

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