Aizawa Naoto 相澤直人

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AIZAWA Naoto 相澤直人

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Researcher Number	70707033
Other IDs	https://orcid.org/0009-0007-6464-8008
Affiliation (Current)	2026: 近畿大学, 原子力研究所, 講師
Affiliation (based on the past Project Information) *help	2019 – 2024: 東北大学, 工学研究科, 助教
Review Section/Research Field	Principal Investigator Basic Section 31010:Nuclear engineering-related Except Principal Investigator Basic Section 31010:Nuclear engineering-related
Keywords	Principal Investigator 核変換 / 中性子スペクトル / 原子炉設計 / 放射性廃棄物 / 長寿命核分裂生成物 / マイナーアクチノイド / フッ化物溶融塩 / 炉心設計 / 核分裂生成物 / マイナーアクチニド … More / 溶融塩炉 / 原子炉実験 / 放射化反応率 / 放射化反応 / 加速器駆動システム / 中速中性子 / 中性子核反応 … More Except Principal Investigator 原子力安全 / ソースターム / 燃焼・放射化計算 / 加速器駆動未臨界炉 / 高温ガス炉 / 高速炉 / 軽水炉 / 中性子スペクトル / ORIGEN / 固有直交分解(POD) / 燃焼計算 Less

Development of fast and accurate advanced burnup and activation calculation method for nuclear safety
- Principal Investigator
  
  山本章夫
- Project Period (FY)
  2024 – 2026
- Research Category
  
  Grant-in-Aid for Scientific Research (C)
- Review Section
  
  Basic Section 31010:Nuclear engineering-related
- Research Institution
  Nagoya University
Challenge for the Realization of Highly Safe Zero-emission Molten Salt Reactor SystemPrincipal Investigator
- Principal Investigator
  
  Aizawa Naoto
- Project Period (FY)
  2022 – 2024
- Research Category
  
  Grant-in-Aid for Scientific Research (C)
- Review Section
  
  Basic Section 31010:Nuclear engineering-related
- Research Institution
  Tohoku University
Challenge for the complete control of neutron reaction -Creation of flexible neutron spectrum fieldPrincipal Investigator
- Principal Investigator
  
  AIZAWA Naoto
- Project Period (FY)
  2019 – 2022
- Research Category
  
  Grant-in-Aid for Early-Career Scientists
- Review Section
  
  Basic Section 31010:Nuclear engineering-related
- Research Institution
  Tohoku University

All 2025 2024 2023 2022 2021 2020

All Journal Article Presentation

[Journal Article] Neutronics Design of Molten Salt Reactor for Transmutation of Various Radioactive Nuclides2024
- Author(s)
  Koji Fujikura, Naoto Aizawa
- Journal Title
  
  Proceedings of the 2024 31st International Conference on Nuclear Engineering.
  
  Volume: Volume 11
- DOI
  10.1115/icone31-134875
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-22K04980
[Journal Article] Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF2-ZrF4-UF4 System2024
- Author(s)
  Naoto Aizawa, Hiroki Shishido, Koji Fujikura
- Journal Title
  
  Proceedings of the 2024 31st International Conference on Nuclear Engineering
  
  Volume: Volume 4
- DOI
  10.1115/icone31-134672
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-22K04980
[Journal Article] Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores2023
- Author(s)
  Naoto Aizawa, Cheol Ho Pyeon
- Journal Title
  
  Nuclear Science and Engineering
  
  Volume: - Issue: 3 Pages: 658-672
- DOI
  10.1080/00295639.2023.2212580
- Peer Reviewed
- Data Source
  KAKENHI-PROJECT-19K15474
[Journal Article] Measurement of Reaction Rate of Intermediate Neutrons on Critical Core with Various Neutron Spectra Zone2021
- Author(s)
  N. Aizawa, H. Akatsu,T. Abe, K. Kawabata, C. H. Pyeon
- Journal Title
  
  KURRI Progress Report 2020
  
  Volume: - Pages: 103-103
- Open Access
- Data Source
  KAKENHI-PROJECT-19K15474
[Presentation] PODを用いた中性子スペクトル再構成に基づく燃焼計算手法の開発 1. 軽水炉UO2燃料における適用性検討2025
- Author(s)
  渡邉友章, 相澤直人, 千葉豪, 多田健一, 山本章夫
- Organizer
  日本原子力学会　2025年春の年会
- Data Source
  KAKENHI-PROJECT-24K08300
[Presentation] PODを用いた中性子スペクトル再構成に基づく燃焼計算手法の開発 2. 高速炉における適用性検討2025
- Author(s)
  相澤直人, 渡邉友章, 千葉豪, 多田健一
- Organizer
  日本原子力学会　2025年春の年会
- Data Source
  KAKENHI-PROJECT-24K08300
[Presentation] 燃料組成の調整による可変スペクトル溶融塩炉の研究 (2) 分子動力学法を用いたLiF-BeF2-ZrF4-UF4混合溶融塩の密度評価2024
- Author(s)
  宍戸博紀, 橋爪秀利, 相澤直人
- Organizer
  日本原子力学会2024年春の年会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] 燃料組成の調整による可変スペクトル溶融塩炉の研究 (1) 基本概念および臨界解析2024
- Author(s)
  相澤直人, 宍戸博紀, 藤倉洪治
- Organizer
  日本原子力学会2024年春の年会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] Neutronics Design of Molten Salt Reactor for Transmutation of Various Radioactive Nuclides2024
- Author(s)
  Koji Fujikura, Naoto Aizawa
- Organizer
  The 31st International Conference on Nuclear Engineering
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] 多様な放射性核種の核変換のためのフッ化物溶融塩炉の炉心核設計2024
- Author(s)
  藤倉洪治, 相澤直人
- Organizer
  日本原子力学会2024年春の年会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF2-ZrF4-UF4 System2024
- Author(s)
  Naoto Aizawa, Hiroki Shishido, Koji Fujikura
- Organizer
  The 31st International Conference on Nuclear Engineering
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] フッ化物溶融塩炉における核変換性能・臨界性に対する核データライブラリの影響の解析2024
- Author(s)
  藤倉洪治, 相澤直人
- Organizer
  日本原子力学会2024年秋の大会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] フッ化物溶融塩炉における長寿命核分裂生成物の燃焼解析2023
- Author(s)
  藤倉洪治、相澤直人
- Organizer
  日本原子力学会2023年春の年会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] Effect of Nuclear Data Library on Criticality and Transmutation Characteristics in Fluoride Molten Salt Reactor2023
- Author(s)
  Koji FUJIKURA, Naoto AIZAWA
- Organizer
  The 12th International Conference on Nuclear Criticality Safety (INCN2023)
- Int'l Joint Research
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] フッ化物溶融塩炉における長寿命核分裂生成物の燃焼特性に関する研究2022
- Author(s)
  藤倉洪治、相澤直人
- Organizer
  日本原子力学会東北支部第46回研究交流会
- Data Source
  KAKENHI-PROJECT-22K04980
[Presentation] 原子炉実験における熱外中性子ー中速中性子による放射化反応率の影響 (2) 仮想未臨界実験体系における数値解析2022
- Author(s)
  相澤直人, 河端恒介
- Organizer
  日本原子力学会2022年秋の大会
- Data Source
  KAKENHI-PROJECT-19K15474
[Presentation] 原子炉実験における熱外中性子ー中速中性子による放射化反応率の影響 (1)臨界体系における反応率測定ならびに解析2021
- Author(s)
  相澤直人，卞哲浩
- Organizer
  日本原子力学会2021年秋の年会
- Data Source
  KAKENHI-PROJECT-19K15474
[Presentation] 加速器駆動システム実験における中性子スペクトルに対する未臨界度の影響2020
- Author(s)
  相澤直人，山中正朗，卞哲浩
- Organizer
  日本原子力学会2020年秋の大会
- Data Source
  KAKENHI-PROJECT-19K15474

1. 宍戸博紀 (90827792)

# of Collaborated Projects: 1 results

# of Collaborated Products: 4 results
2. 山本章夫 (50362265)

# of Collaborated Projects: 1 results

# of Collaborated Products: 1 results
3. 渡邉友章 (30991236)

# of Collaborated Projects: 1 results

# of Collaborated Products: 2 results
4. 千葉豪 (50421524)

# of Collaborated Projects: 1 results

# of Collaborated Products: 2 results

Aizawa Naoto 相澤 直人

AIZAWA Naoto 相澤 直人

Research Projects

Research Products

Co-Researchers

Development of fast and accurate advanced burnup and activation calculation method for nuclear safety

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

Challenge for the Realization of Highly Safe Zero-emission Molten Salt Reactor SystemPrincipal Investigator

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

Challenge for the complete control of neutron reaction -Creation of flexible neutron spectrum fieldPrincipal Investigator

Principal Investigator

Project Period (FY)

Research Category

Review Section

Research Institution

[Journal Article] Neutronics Design of Molten Salt Reactor for Transmutation of Various Radioactive Nuclides2024

Author(s)

Journal Title

DOI

Data Source

[Journal Article] Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF2-ZrF4-UF4 System2024

Author(s)

Journal Title

DOI

Data Source

[Journal Article] Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores2023

Author(s)

Journal Title

DOI

Data Source

[Journal Article] Measurement of Reaction Rate of Intermediate Neutrons on Critical Core with Various Neutron Spectra Zone2021

Author(s)

Journal Title

Data Source

[Presentation] PODを用いた中性子スペクトル再構成に基づく燃焼計算手法の開発 1. 軽水炉UO2燃料における適用性検討2025

Author(s)

Organizer

Data Source

[Presentation] PODを用いた中性子スペクトル再構成に基づく燃焼計算手法の開発 2. 高速炉における適用性検討2025

Author(s)

Organizer

Data Source

[Presentation] 燃料組成の調整による可変スペクトル溶融塩炉の研究 (2) 分子動力学法を用いたLiF-BeF2-ZrF4-UF4混合溶融塩の密度評価2024

Author(s)

Organizer

Data Source

[Presentation] 燃料組成の調整による可変スペクトル溶融塩炉の研究 (1) 基本概念および臨界解析2024

Author(s)

Organizer

Data Source

[Presentation] Neutronics Design of Molten Salt Reactor for Transmutation of Various Radioactive Nuclides2024

Author(s)

Organizer

Data Source

[Presentation] 多様な放射性核種の核変換のためのフッ化物溶融塩炉の炉心核設計2024

Author(s)

Organizer

Data Source

[Presentation] Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF2-ZrF4-UF4 System2024

Author(s)

Organizer

Data Source

[Presentation] フッ化物溶融塩炉における核変換性能・臨界性に対する核データライブラリの影響の解析2024

Author(s)

Organizer

Data Source

[Presentation] フッ化物溶融塩炉における長寿命核分裂生成物の燃焼解析2023

Author(s)

Organizer

Data Source

[Presentation] Effect of Nuclear Data Library on Criticality and Transmutation Characteristics in Fluoride Molten Salt Reactor2023

Author(s)

Aizawa Naoto 相澤直人

AIZAWA Naoto 相澤直人