Takamatsu Kuniyoshi 高松邦吉

… Alternative Names

高松邦吉タカマツクニヨシ

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Researcher Number	70414547
Other IDs	https://orcid.org/0000-0002-7967-1899
Affiliation (Current)	2025: 国立研究開発法人日本原子力研究開発機構, エネルギー研究開発領域高温ガス炉プロジェクト推進室, 研究主幹
Affiliation (based on the past Project Information) *help	2023: 国立研究開発法人日本原子力研究開発機構, 高温ガス炉プロジェクト推進室, 研究主幹 2022: 国立研究開発法人日本原子力研究開発機構, 高速炉・新型炉研究開発部門炉設計部, 研究主幹 2018 – 2020: 国立研究開発法人日本原子力研究開発機構, 高速炉・新型炉研究開発部門大洗研究所高温ガス炉研究開発センター, 研究副主幹 2015 – 2017: 国立研究開発法人日本原子力研究開発機構, 原子力科学研究部門高温ガス炉水素・熱利用研究センター, 研究副主幹
Review Section/Research Field	Principal Investigator Basic Section 25020:Safety engineering-related / Basic Section 31010:Nuclear engineering-related / Nuclear engineering
Keywords	Principal Investigator 高温ガス炉 / 受動的安全性 / 格納容器 / 対流 / ふく射 / 熱工学 / 原子力工学 / 新型炉 / HTGR / 自然対流 … More / 輻射 / 冷却設備 / 安全工学 / 伝熱 / HTTR / 崩壊熱 / 熱伝導 Less

Basic/Fundamental Research on Safety Features of Passive Cooling Systems for Reactor Pressure VesselPrincipal Investigator
- Principal Investigator
  
  高松邦吉
- Project Period (FY)
  2022 – 2024
- Research Category
  
  Grant-in-Aid for Scientific Research (C)
- Review Section
  
  Basic Section 25020:Safety engineering-related
- Research Institution
  Japan Atomic Energy Agency
Innovative reactor cavity cooling system using passive radiative cooling to prevent meltdownsPrincipal Investigator
- Principal Investigator
  
  Takamatsu Kuniyoshi
- Project Period (FY)
  2018 – 2020
- Research Category
  
  Grant-in-Aid for Scientific Research (C)
- Review Section
  
  Basic Section 31010:Nuclear engineering-related
- Research Institution
  Japan Atomic Energy Agency
A novel reactor cavity cooling system (RCCS) with passive safety featuresPrincipal Investigator
- Principal Investigator
  
  Takamatsu Kuniyoshi
- Project Period (FY)
  2015 – 2017
- Research Category
  
  Grant-in-Aid for Scientific Research (C)
- Research Field
  
  Nuclear engineering
- Research Institution
  Japan Atomic Energy Agency

All 2024 2023 2022 2021 2019 2018 2017 2016 2015

All Journal Article Presentation Book

[Book] 革新的冷却技術～メカニズムから素子・材料・システム開発まで～2024
- Author(s)
  高松邦吉、他29名
- Total Pages
  272
- Publisher
  （株）エヌ・ティー・エス
- ISBN
  9784860438548
- Data Source
  KAKENHI-PROJECT-22K04628
[Journal Article] Comparison on Safety Features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)2024
- Author(s)
  Takamatsu Kuniyoshi、Funatani Shumpei
- Journal Title
  
  Nuclear Engineering and Technology
  
  Volume: 56 Issue: 3 Pages: 832-845
- DOI
  10.1016/j.net.2023.09.036
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-22K04628
[Journal Article] Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation2021
- Author(s)
  Takamatsu Kuniyoshi、Matsumoto Tatsuya、Liu Wei、Morita Koji
- Journal Title
  
  Annals of Nuclear Energy
  
  Volume: 151 Pages: 107867-107867
- DOI
  10.1016/j.anucene.2020.107867
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-18K05000
[Journal Article] Comparative methodology between actual RCCS and downscaled heat-removal test facility2019
- Author(s)
  Takamatsu Kuniyoshi、Matsumoto Tatsuya、Liu Wei、Morita Koji
- Journal Title
  
  Annals of Nuclear Energy
  
  Volume: 133 Pages: 830-836
- DOI
  10.1016/j.anucene.2019.07.025
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-18K05000
[Journal Article] 6-4 受動的放射冷却を用いた高温ガス炉の冷却設備を開発－事故時崩壊熱除去方法の概念成立に向けて－2018
- Author(s)
  高松邦吉
- Journal Title
  
  原子力機構の研究開発成果 2018-19
  
  Volume: - Pages: 67-67
- Open Access
- Data Source
  KAKENHI-PROJECT-18K05000
[Journal Article] Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection2018
- Author(s)
  Takamatsu Kuniyoshi、Matsumoto Tatsuya、Liu Wei、Morita Koji
- Journal Title
  
  Annals of Nuclear Energy
  
  Volume: 122 Pages: 201-206
- DOI
  10.1016/j.anucene.2018.08.047
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-18K05000
[Journal Article] New reactor cavity cooling system (RCCS) with passive safety features: A Comparative methodology between a real RCCS and a scaled-down heat-removal test facility2016
- Author(s)
  高松邦吉、松元達也、守田幸路
- Journal Title
  
  Annals of Nuclear Energy
  
  Volume: 96 Pages: 137-147
- DOI
  10.1016/j.anucene.2016.05.012
- Peer Reviewed / Acknowledgement Compliant
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] Improvement of cooling performance of reactor pressure vessel using passive cooling2023
- Author(s)
  Banno Masaki、Funatani Shumpei、Takamatsu Kuniyoshi
- Organizer
  30th International Conference on Nuclear Engineering (ICONE 30)
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-22K04628
[Presentation] Comparison on safety features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)2023
- Author(s)
  Takamatsu Kuniyoshi、Funatani Shumpei
- Organizer
  2023 International Congress on Advances in Nuclear Power Plants
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-22K04628
[Presentation] 輻射を利用した原子力キャビティ冷却システムの伝熱特性に関する研究2022
- Author(s)
  坂野雅樹、舩谷俊平、高松邦吉
- Organizer
  山梨講演会2022
- Data Source
  KAKENHI-PROJECT-22K04628
[Presentation] 受動的冷却機能を持つ原子炉圧力容器冷却設備に関する研究2022
- Author(s)
  高松邦吉、舩谷俊平、坂野雅樹
- Organizer
  日本原子力学会 2022年秋の大会
- Data Source
  KAKENHI-PROJECT-22K04628
[Presentation] ふく射を利用した原子炉キャビティ冷却シスムの伝熱特性に関する研究2019
- Author(s)
  西森友弥、明石知泰、宇和田尚悟、松元達也、劉維、守田幸路、高松邦吉
- Organizer
  日本原子力学会九州支部第38回研究発表講演会
- Data Source
  KAKENHI-PROJECT-18K05000
[Presentation] Experimental study on heat removal performance of a new reactor cavity cooling system (RCCS)2018
- Author(s)
  Hosomi Seisuke、Akashi Tomoyasu、Matsumoto Tatsuya、Liu Wei、Morita Koji、Takamatsu Kuniyoshi
- Organizer
  The 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11)
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-18K05000
[Presentation] 高温ガス炉における受動的冷却設備の伝熱特性に関する検討2018
- Author(s)
  明石知泰、細見成祐、井福弘基、松元達也、劉維、守田幸路、高松邦吉
- Organizer
  日本原子力学会九州支部第37回研究発表講演会
- Data Source
  KAKENHI-PROJECT-18K05000
[Presentation] 高温ガス炉における受動的冷却設備の伝熱特性に関する検討2018
- Author(s)
  細見成祐、山口修平、明石知泰、松元達也、劉維、守田幸路、高松邦吉
- Organizer
  日本原子力学会　2018年春の年会
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を持つ新しい炉容器冷却設備のスケールモデルによる伝熱特性に関する実験的検討2017
- Author(s)
  山口修平、佐藤紀恭、松元達也、守田幸路、高松邦吉
- Organizer
  九州大学エネルギーウィーク 2017
- Place of Presentation
  九州大学伊都キャンパス　（福岡県・福岡市）
- Year and Date
  2017-01-31
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を持つ新しい炉容器冷却設備 (2)スケールモデルによる伝熱特性に関する実験的検討2016
- Author(s)
  佐藤紀恭、山口修平、松元達也、守田幸路、高松邦吉
- Organizer
  日本原子力学会 2016年秋の大会
- Place of Presentation
  久留米シティプラザ　（福岡県・久留米市）
- Year and Date
  2016-09-07
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] New reactor cavity cooling system with a novel shape and passive safety featureｓ2016
- Author(s)
  高松邦吉、松元達也、守田幸路
- Organizer
  2016 International Congress on Advances in Nuclear Power Plants (ICAPP 2016)
- Place of Presentation
  サンフランシスコ　（アメリカ）
- Year and Date
  2016-04-17
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を持つ新しい炉容器冷却設備 (1)実機のRCCSと比較するために等倍縮小した除熱試験装置の実験条件2016
- Author(s)
  高松邦吉、松元達也、守田幸路
- Organizer
  日本原子力学会 2016年秋の大会
- Place of Presentation
  久留米シティプラザ　（福岡県・久留米市）
- Year and Date
  2016-09-07
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を持つ新しい炉容器冷却設備 - 実機のRCCS と等倍縮小した除熱試験装置の比較方法 -2016
- Author(s)
  高松邦吉、松元達也、守田幸路
- Organizer
  日本原子力学会 2016年春の年会
- Place of Presentation
  東北大学　（宮城県・仙台市）
- Year and Date
  2016-03-26
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を有する原子炉圧力容器冷却設備の伝熱特性に関する研究: スケールモデルによる実験的検討2016
- Author(s)
  山口修平、佐藤紀恭、松元達也、守田幸路、高松邦吉
- Organizer
  日本原子力学会九州支部第35回研究発表講演会
- Place of Presentation
  九州大学筑紫キャンパス　（福岡県・春日市）
- Year and Date
  2016-12-03
- Data Source
  KAKENHI-PROJECT-15K06676
[Presentation] 受動的安全性を持つ新しい炉容器冷却設備2015
- Author(s)
  高松邦吉、松元達也、守田幸路
- Organizer
  日本原子力学会 2015年秋の大会
- Place of Presentation
  静岡大学　（静岡県・静岡市）
- Year and Date
  2015-09-09
- Data Source
  KAKENHI-PROJECT-15K06676

1. 守田幸路 (40311849)

# of Collaborated Projects: 2 results

# of Collaborated Products: 15 results
2. 松元達也 (90325514)

# of Collaborated Projects: 2 results

# of Collaborated Products: 15 results
3. 劉維 (70446417)

# of Collaborated Projects: 1 results

# of Collaborated Products: 6 results
4. 舩谷俊平 (50607588)

# of Collaborated Projects: 1 results

# of Collaborated Products: 5 results

Takamatsu Kuniyoshi 高松 邦吉

高松 邦吉 タカマツ クニヨシ

Research Projects

Research Products

Co-Researchers

Basic/Fundamental Research on Safety Features of Passive Cooling Systems for Reactor Pressure VesselPrincipal Investigator

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

Innovative reactor cavity cooling system using passive radiative cooling to prevent meltdownsPrincipal Investigator

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

A novel reactor cavity cooling system (RCCS) with passive safety featuresPrincipal Investigator

Principal Investigator

Project Period (FY)

Research Category

Research Field

Research Institution

[Book] 革新的冷却技術～メカニズムから素子・材料・システム開発まで～2024

Author(s)

Total Pages

Publisher

ISBN

Data Source

[Journal Article] Comparison on Safety Features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)2024

Author(s)

Journal Title

DOI

Data Source

[Journal Article] Comparison between passive reactor cavity cooling systems based on atmospheric radiation and atmospheric natural circulation2021

Author(s)

Journal Title

DOI

Data Source

[Journal Article] Comparative methodology between actual RCCS and downscaled heat-removal test facility2019

Author(s)

Journal Title

DOI

Data Source

[Journal Article] 6-4 受動的放射冷却を用いた高温ガス炉の冷却設備を開発－事故時崩壊熱除去方法の概念成立に向けて－2018

Author(s)

Journal Title

Data Source

[Journal Article] Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection2018

Author(s)

Journal Title

DOI

Data Source

[Journal Article] New reactor cavity cooling system (RCCS) with passive safety features: A Comparative methodology between a real RCCS and a scaled-down heat-removal test facility2016

Author(s)

Journal Title

DOI

Data Source

[Presentation] Improvement of cooling performance of reactor pressure vessel using passive cooling2023

Author(s)

Organizer

Data Source

[Presentation] Comparison on safety features among HTGR’s Reactor Cavity Cooling Systems (RCCSs)2023

Author(s)

Organizer

Data Source

[Presentation] 輻射を利用した原子力キャビティ冷却システムの伝熱特性に関する研究2022

Author(s)

Organizer

Data Source

[Presentation] 受動的冷却機能を持つ原子炉圧力容器冷却設備に関する研究2022

Author(s)

Organizer

Data Source

[Presentation] ふく射を利用した原子炉キャビティ冷却シスムの伝熱特性に関する研究2019

Author(s)

Organizer

Data Source

[Presentation] Experimental study on heat removal performance of a new reactor cavity cooling system (RCCS)2018

Author(s)

Takamatsu Kuniyoshi 高松邦吉

高松邦吉タカマツクニヨシ