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Narukawa Takafumi  成川 隆文

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成川 隆文  ナルカワ タカフミ

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Researcher Number 30714208
Other IDs
Affiliation (Current) 2026: 東京大学, 大学院工学系研究科(工学部), 助教
2026: 国立研究開発法人日本原子力研究開発機構, 原子力安全・防災研究所 安全研究センター, 非常勤嘱託
Affiliation (based on the past Project Information) *help 2023 – 2024: 東京大学, 大学院工学系研究科(工学部), 助教
Review Section/Research Field
Principal Investigator
Basic Section 31010:Nuclear engineering-related
Keywords
Principal Investigator
情報量規準 / ベイズモデリング / 冷却性 / モンテカルロシミュレーション / 燃料破損 / 最適評価 / 炉心損傷判定基準 / 不確かさ / 原子力安全 / リスク評価
  • Research Projects

    (1 results)
  • Research Products

    (8 results)
  •  合理的なリスク評価のための不確かさを考慮した炉心損傷判定基準の最適評価法の確立Principal Investigator

    • Principal Investigator
      成川 隆文
    • Project Period (FY)
      2023 – 2025
    • Research Category
      Grant-in-Aid for Early-Career Scientists
    • Review Section
      Basic Section 31010:Nuclear engineering-related
    • Research Institution
      The University of Tokyo

All 2025 2024 2023

All Journal Article Presentation

  • [Journal Article] Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident2025

    • Author(s)
      Tanaka Hiroki、Narukawa Takafumi、Takata Takashi
    • Journal Title

      Journal of Nuclear Engineering

      Volume: 6 Issue: 1 Pages: 6-6

    • DOI

      10.3390/jne6010006

    • Peer Reviewed / Open Access
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Journal Article] Hierarchical Bayesian modeling to quantify fracture limit uncertainty of high-burnup advanced fuel cladding tubes under loss-of-coolant accident conditions2023

    • Author(s)
      Narukawa Takafumi、Hamaguchi Shusuke、Takata Takashi、Udagawa Yutaka
    • Journal Title

      Nuclear Engineering and Design

      Volume: 411 Pages: 112443-112443

    • DOI

      10.1016/j.nucengdes.2023.112443

    • Peer Reviewed
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] リスク情報を活用した合理的な意思決定に向けたPRA手法の高度化に関する研究,2025

    • Author(s)
      成川隆文
    • Organizer
      日本原子力学会2025年春の年会
    • Invited
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] A Bayesian Approach for Designing Experiments Based on Information Criteria to Reduce Prediction Uncertainty of Fuel Fracture during LOCA2024

    • Author(s)
      Hamaguchi Shusuke, Narukawa Takafumi、Takata Takashi
    • Organizer
      Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024)
    • Int'l Joint Research
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] 確率論的モデルを用いた燃料棒破断の最適評価に関する研究2024

    • Author(s)
      田中 裕暉、成川 隆文、高田 孝
    • Organizer
      日本原子力学会2024年春の年会
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] Probabilistic Approach for Best Estimate of Fuel Rod Fracture2024

    • Author(s)
      Tanaka Hiroki、Narukawa Takafumi、Takata Takashi
    • Organizer
      Probabilistic Safety Assessment and Management 17 & Asian Symposium on Risk Assessment and Management 2024 (PSAM17&ASRAM2024)
    • Int'l Joint Research
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] Uncertainty Analysis of Model Selection Based on Information Criterion: A Case Study of a Probability Estimation Model for Fuel Cladding Tube Fracture during LOCA2024

    • Author(s)
      Narukawa Takafumi、Yutaka Udagawa
    • Organizer
      27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27)
    • Int'l Joint Research
    • Data Source
      KAKENHI-PROJECT-23K13685
  • [Presentation] Epistemic Uncertainty Reduction in Fuel Fracture Limit during LOCA through Bayesian Updating Based on Information Criterion2023

    • Author(s)
      Narukawa Takafumi、Hamaguchi Shusuke、Takata Takashi
    • Organizer
      Asian Symposium on Risk Assessment and Management 2023 (ASRAM 2023)
    • Int'l Joint Research
    • Data Source
      KAKENHI-PROJECT-23K13685

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