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Fujita Tatsuya
| Faculty of Engineering Applied Quantum Science and Engineering Quantum Energy Engineering | Associate Professor |
Researcher basic information
■ Degree■ URL
researchmap URLホームページURL■ Various IDs
Researcher number
- 71012902
Research Keyword
- Nuclide Depletion Analysis
- Transient Analysis
- Criticality Safety
- Uncertainty Quantification
- LWR Core Analysis
- Reactor Physics
- Bachelor's degree program, School of Engineering
- Master's degree program, Graduate School of Engineering
- Doctoral (PhD) degree program, Graduate School of Engineering
Career
■ CareerCareer
- Oct. 2023 - Sep. 2024
Japan Atomic Energy Agency, Nuclear Safety Research Center, Sector of Nuclear Safety Research and Emergency Preparedness, Senior Post-Doctral Fellow, Japan - Sep. 2021 - Sep. 2023
Nuclear Regulation Authority, Regulatory Standard and Research Division, Regulatory Standard and Research Department - May 2015 - Aug. 2021
Nuclear Regulation Authority, Division of Research for Reactor System Safety, Regulatory Standard and Research Department - Apr. 2014 - May 2015
Nuclear Regulation Authority, Regulatory Standard and Research Division, Regulatory Standard and Research Department
Research activity information
■ Awards- Dec. 2019, 原子力規制委員会, 原子力規制委員会表彰（論文表彰）
藤田達也 - Sep. 2019, 日本原子力学会炉物理部会, 日本原子力学会炉物理部会賞奨励賞
国産核データJENDL-4.0およびCASMO5/TRACE/PARCSを用いたSPERT-III実験の解析および不確かさ評価
藤田 達也
- Comparison of Burnup Credit Loading Curve Methodologies for a Simplified Case with PWR Fuel: introduction to OECD/NEA/NSC/WPNCS SG13 study
Alexander Vasiliev; Matthias Frankl; David Hanlon; Magda Stefanowska Skrodzka; Dirk Schulze Grachtrup; Gábor Hordósy; Miriam Vazquez; Dennis Mennerdahl; Axel Hoefer; Fabian Sommer; Barthélémi Petillon; Liam Payne; Tatsuya Fujita; Tomoaki Watanabe; Marjan Kromar; Dušan Čalič; Andrej Trkov; Ahmed Shama; Madalina Wittel; Charles Bory; Marcel Tardy; Coralie Carmouze; Tangi Nicol; Alex Shaw; B.J. Marshall; Shane Har; Justin Clarity; Casey Spitz; Péter Buday; Pedro Ortego; Candan Töre; Maksym Chernykh; Sven Tittelbach
Proceedings of International Conference on Physics of Reactors (PHYSOR2026), Apr. 2026
English, International conference proceedings - Fundamental Study on Dimension Reduction of Covariance Matrix Modified by Data Assimilation
Yuta Aizawa; Tatsuya Fujita
Proceedings of International Conference on Physics of Reactors (PHYSOR2026), Apr. 2026, [Last author]
English, International conference proceedings, 50135413 - Investigation of Effective Cross Section Generation in FRENDY-V2/GENESIS for Three-Dimensional LWR Lattice Problems
Tatsuya Fujita
Proceedings of International Conference on Physics of Reactors (PHYSOR2026), Apr. 2026, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Special issue on progressive reactor physics for current and future challenges
Kenichi Tada; Naoto Aizawa; Tatsuya Fujita; Masahiro Fukushima; Cheol Ho Pyeon
Journal of Nuclear Science and Technology, 63, 1, 1, 2, Informa UK Limited, 2026
English, Scientific journal - Burnup calculation using POD-based neutron spectrum reconstruction
Tomoaki Watanabe; Naoto Aizawa; Go Chiba; Kenichi Tada; Tatsuya Fujita; Akio Yamamoto
Journal of Nuclear Science and Technology, 63, 2, 166, 186, Informa UK Limited, 2026, [Peer-reviewed]
English, Scientific journal - Development of quick neutron spectrum reconstruction module based on POD for burnup calculation of fast reactor
Naoto AIZAWA; Tomoaki WATANABE; Go CHIBA; Kenichi TADA; Tatsuya FUJITA; Akio YAMAMOTO
Nuclear Engineering and Technology, 58, 5, 104176, Elsevier BV, 2026, [Peer-reviewed]
English, Scientific journal - Nuclear data sensitivity analysis on LWR nuclear fuel depletion with the modern evaluated nuclear data libraries
Hidayati Amar; Go Chiba; Tatsuya Fujita; Junshuang Fan; Yuya Inagaki
Journal of Nuclear Science and Technology, 63, 2, 216, 226, Informa UK Limited, 2026, [Peer-reviewed]
English, Scientific journal - Preliminary Investigation of Dancoff Factor Treatment in Application of Direct Coupling Code System Using FRENDY version 2 and GENESIS on Three-Dimensional LWR Fuel Assembly Problem
Tatsuya Fujita; Go Chiba
Proceedings of International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering 2025 (M&C 2025), Apr. 2025, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices
Tatsuya Fujita; Akio Yamamoto
Journal of Nuclear Science and Technology, 62, 2, 179, 196, 2025, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Estimation of influence of implicit effect due to multi-group cross-section perturbations on uncertainty analysis in PWR-UO 2 and -MOX lattice calculations
Tatsuya Fujita
Journal of Nuclear Science and Technology, 62, 8, 731, 739, Informa UK Limited, 2025, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - A Preliminary uncertainty analysis of PWR depletion numerical test problem on OECD/NEA/NSC LWR-UAM benchmark phase II based on JENDL-5
Tatsuya Fujita
Proceedings of Best Estimate Plus Uncertainty International Conference (BEPU 2024) (Internet), 14, May 2024, [Peer-reviewed], [Lead author, Corresponding author]
English, The uncertainty analysis of PWR depletion test problem on the OECD/NEA/NSC LWR-UAM benchmark Phase II based on JENDL-5 was performed as a preliminary investigation. The random sampling was used to quantify the uncertainty of k-infinity and nuclide inventories, the cross section (XS), the fission product yield (FPY), the decay constant, and the decay branch ratio were randomly perturbed, and several times of SERPENT 2.2.1 calculations were performed. XSs in the ACE file were perturbed by the ACE file perturbation tool using FRENDY with the 56-group covariance matrix generated by NJOY2016.72. The perturbation quantity of independent FPY was evaluated using the FPY covariance matrix prepared in JENDL-5, and the perturbed cumulative FPY was reconstructed based on the relationship between the independent and cumulative FPYs. The decay constant was independently perturbed for each nuclide. To perturb the decay branch ratios, the covariance matrix was generated by applying the generalized least square method and randomly perturbed based on this covariance matrix in the same manner as the independent FPY. In general, the influence due to decay data was an order of magnitude smaller than the influences due to XS and FPY uncertainties. For the uncertainty of k-infinity and transuranic nuclide inventories, the influence due to XS uncertainty was dominant, and that due to FPY and decay data uncertainties was one or a few orders of magnitude smaller. On the other hand, for the uncertainty of FP nuclide inventories, the influence due to FPY uncertainty was almost the same or larger than that due to XS uncertainty. It was also confirmed that the influence due to either XS or FPY uncertainty became different for each FP nuclide. In future studies, the influence due to XS uncertainty on FP nuclides will be discussed because it was not prepared in JENDL-5 and not considered in the present paper. - A Comparative study of efficient sampling techniques for uncertainty quantification due to cross-section covariance data
Tatsuya Fujita
Proceedings of International Conference on Physics of Reactors (PHYSOR 2024) (Internet), 718, 727, Apr. 2024, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings, The convergence process of the k-infinity uncertainty during random-sampling-based uncertainty quantification was compared between several efficient sampling techniques. The k-infinity uncertainty was evaluated by statistically processing several times of SERPENT 2.2.1 calculations using perturbed ACE files based on JENDL-5 cross-section covariance data. The antithetic sampling (AS), the Latin hypercube sampling (LHS), the control variates (CV), and the combination approaches of them were focused on in the present paper. In PWR-UO$_{2}$ fuel assembly geometry without the nuclide depletion, as discussed in past studies, AS and LHS showed higher efficient convergence than nominal sampling without any efficient sampling techniques. In terms of CV, though a stand-alone application did not have a large impact on the k-infinity uncertainty convergence, its performance was improved in combination with AS, as discussed in the past study. In addition, a new combined approach of LHS and CV (CV+LHS) was proposed in the present paper. CV+LHS improved the k-infinity uncertainty convergence and was more efficient than CV+AS. The main reason for this improvement was that the convergence for the mean value of alternative parameters in CV was enhanced by applying LHS. Consequently, this study proposed the new combined approach of CV+LHS and confirmed its efficiency performance for the random-sampling-based uncertainty quantification in the PWR-UO$_{2}$ fuel assembly geometry. The applicability of CV+LHS for the nuclide-depletion calculations will be confirmed in future studies. - Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code
Tatsuya Fujita
Journal of Nuclear Science and Technology, 61, 5, 679, 692, 2024, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0
Tatsuya Fujita
Journal of Nuclear Science and Technology, 61, 3, 417, 427, 2024, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries
Tatsuya Fujita
Journal of Nuclear Science and Technology, 60, 9, 1143, 1153, 2023, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Influence of manufacturing uncertainty treatment on neutronics uncertainty analysis for lattice physics parameters in PWR-UO2 fuel assembly
Tatsuya Fujita
Journal of Nuclear Science and Technology, 60, 12, 1526, 1537, 2023, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - A manufacturing tolerance influence on MOX lattice physics parameters using FUBILA experiment data
Tatsuya Fujita
International Conference on Physics of Reactors 2022 (PHYSOR2022), 2022, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Analysis of the beavrs benchmark using CASMO5/SIMULATE5 with JENDL-4.0 and ENDF/B-VII.1
Tatsuya Fujita; Tomohiro Sakai
International Conference on Physics of Reactors 2020 (PHYSOR2020), 2020, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Uncertainty analysis of the OECD/NEA LWR UAM benchmark Phase I using CASMO5 with JENDL-4.0 and ENDF/B-VII.1
Tatsuya Fujita; Tomohiro Sakai
Journal of Nuclear Science and Technology, 57, 7, 858, 873, Taylor & Francis, 2020, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Analysis of the SPERT-III E-Core experiment using CASMO5/TRACE/PARCS based on JENDL-4.0 and ENDF/B-VII.1
Tatsuya Fujita; Tomohiro Sakai
Journal of Nuclear Science and Technology, 56, 6, 553, 571, Taylor & Francis, 2019, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Uncertainty analysis of OECD/NEA/NSC UAM benchmark phase I using CASMO5/SIMULATE5 with JENDL-4.0 library and covariance data
Tatsuya Fujita; Tomohiro Sakai
Best Estimate Plus Uncertainty International Conference 2018 (BEPU2018), 2018, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Analysis of the spert-III E-core experiments using CASM05 and TRACE/PARCS CODES with JENDL-4.0 LIBRARY
Tatsuya Fujita; Tomohiro Sakai
International Conference on Physics of Reactors 2018 (PHYSOR2018), 2018, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Study on Cross Section Generation for BWR Pin-by-Pin Core Analysis
Tatsuya Fujita
Doctoral Thesis, Mar. 2015, [Lead author, Corresponding author]
English, Doctoral thesis - Application of correction technique using leakage index combined with SPH or discontinuity factors for energy collapsing on pin-by-pin BWR core analysis
Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto
Journal of Nuclear Science and Technology, 52, 3, 355, 370, Taylor & Francis, 2015, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - A new technique for spectral interference correction on pin-by-pin BWR core analysis
Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto
Journal of Nuclear Science and Technology, 51, 6, 783, 797, Taylor & Francis, 2014, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - A macroscopic cross-section model for BWR pin-by-pin core analysis
Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto
Journal of Nuclear Science and Technology, 51, 3, 282, 304, Taylor & Francis, 2014, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Correction technique for coarse group cross sections considering spectral interference effect on pin-by-pin BWR core analysis
Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto
International Congress on Advances in Nuclear Power Plants 2013 (ICAPP2013), 2013, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Correction of spectral interference effect on Pin-by-Pin BWR core analysis
Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto
Transactions of the American Nuclear Society, 107, 1141, 1143, 2012, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - An optimization approach to establish an appropriate energy group structure for BWR pin-by-pin core analysis
Tatsuya Fujita; Kenichi Tada; Tomohiro Endo; Akio Yamamoto; Shinya Kosaka; Go Hirano; Kenichiro Nozaki
Journal of Nuclear Science and Technology, 49, 7, 689, 707, Taylor & Francis, 2012, [Peer-reviewed], [Lead author, Corresponding author]
English, Scientific journal - Application of quick subchannel analysis method for three-dimensional pin-by-pin BWR core calculations
Kenichi Tada; Tatsuya Fujita; Tomohiro Endo; Akio Yamamoto; Shinya Kosaka; Go Hirano; Kenichiro Nozaki
Journal of Nuclear Science and Technology, 48, 12, 1437, 1452, 2011, [Peer-reviewed]
English, Scientific journal - Investigation on macroscopic cross section model for BWR pin-by-pin core analysis
Tatsuya Fujita; Kenichi Tada; Akio Yamamoto; Yoshihiro Yamane; Shinya Kosaka; Gou Hirano
International Conference on the Physics of Reactors 2010 (PHYSOR2010), 2010, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings - Investigation of theoretical approach to establish energy group structure for BWR pin-by-pin core analysis
Tatsuya Fujita; Kazumasa Otsuka; Kenichi Tada; Tomohiro Endo; Akio Yamamoto; Shinya Kosaka; Go Hirano
Transactions of the American Nuclear Society, 103, 721, 723, 2010, [Peer-reviewed], [Lead author, Corresponding author]
English, International conference proceedings
- Proceedings of the 12th International Conference on Nuclear Criticality Safety (ICNC2023); October 1-6, 2023, Sendai International Center, Sendai, Miyagi, Japan
Suyama Kenya; Gunji Satoshi; Watanabe Tomoaki; Araki Shohei; Fukuda Kodai; Shimada Kazuya; Fujita Tatsuya; Ueki Taro; Nguyen H., JAEA-Conf 2024-001, 40, Jul. 2024
The 12th International Conference on Nuclear Criticality Safety (ICNC2023) was held from October 1 to October 6, 2023, at the Sendai International Center (Aobayama, Aoba-ku, Sendai, Miyagi-prefecture 980-0856, Japan), organized by Japan Atomic Energy Agency (JAEA) and co-organized by the Reactor Physics Division of the Atomic Energy Society of Japan (AESJ) and the Nuclear Energy Agency of the Organization for Economic Co-operation and Development (OECD/NEA). 224 presentations passed peer review and 273 technical session registrations, bringing the total number of registered participants to 289, including accompanying persons. Technical tours were also conducted to i) Fukushima Daiichi Nuclear Power Station of TEPCO holdings and Interim Storage Facility Information Center, ii) Nuclear Science Research Institute of JAEA (STACY Renewable Reactor and FCA), iii) NanoTerasu of Tohoku University (synchrotron radiation facility) and Onagawa Nuclear Power Station of Tohoku Electric Power Co., Inc. This report summarizes the conference and compiles the papers that were presented and agreed to be published in the Proceedings., English, Technical report - PHYSOR2024参加報告; 研究機関職員の立場から
藤田 達也, 日本原子力学会炉物理部会報「炉物理の研究」, 77, Jun. 2024
本報告は2024年4月に開催された炉物理に関する国際会議(PHYSOR2024)に関する報告である。炉物理部会報「炉物理の研究」では、大学教員・学生、メーカー技術者、研究機関職員のそれぞれの立場で参加報告を記載する。本報告は、そのうちの研究機関職員の立場から国際会議における発表内容等を記載するものである。, Japanese, Introduction other - 炉物理部会賞受賞記念寄稿「国産核データJENDL-4.0およびCASMO5/TRACE/PARCSを用いたSPERT-III実験の解析および不確かさ評価」
藤田達也, 日本原子力学会炉物理部会報「炉物理の研究」, 72, Mar. 2020, [Lead author, Corresponding author]
Japanese, Introduction other - 第44回炉物理夏期セミナー報告・若手研究会報告「(4)燃料棒単位BWR炉心計算におけるスペクトル干渉効果を考慮した断面積補正」
藤田達也, 日本原子力学会炉物理部会報「炉物理の研究」, 65, Mar. 2013, [Lead author, Corresponding author]
Japanese, Introduction other - 国際会議報告「(3)Modeling Experimentation Validation (MeV) Summer school に参加して」
藤田達也, 日本原子力学会炉物理部会報「炉物理の研究」, 64, Mar. 2012, [Lead author, Corresponding author]
Japanese, Introduction other
- 核データ共分散行列のMOCABAデータ同化における低ランク平方根の逐次更新
藤田 達也
第31回計算工学講演会, Japanese, Oral presentation
Jun. 2026, 50135413 - データ同化後の共分散行列の次元削減（2）Toy Problem での結果
相澤 悠太; 藤田 達也
日本原子力学会2026年春の年会, Japanese, Oral presentation
Mar. 2026, 50135413 - データ同化後の共分散行列の次元削減（1）全体計画とアプローチの方向性
藤田 達也; 相澤 悠太
日本原子力学会2026年春の年会, Japanese, Oral presentation
Mar. 2026, 50135413 - 一般化摂動論を用いた医療用中性子照射装置における多様な物質の配置の最適化
相澤 悠太; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - 原子核の崩壊・生成計算における核種数密度簡易予測モデルの比較
遠藤 想太; 増田 純希; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - PODを活用したエネルギー群構造探索手法 (2) 結果
小嶋 敦志; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - PODを活用したエネルギー群構造探索手法 (1) 理論
小嶋 敦志; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - 離散座標法における適合角度離散化手法でのモーメント保存に関する検討
吉池 裕太; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - 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 (3) 多群実効断面積計算の導入及び361群エネルギー群構造を用いた検証
渡邉 友章; 相澤 直人; 千葉 豪; 多田 健一; 藤田 達也; 山本 章夫
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - 照射後試験データに基づく燃焼感度データベースの整備 (1) CBZによる照射後試験データの解析
増田 純希; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - EFPモデルを用いた即発中性子減衰定数への遅発モードの混入の可能性の検討
三岩 深悟; 千葉 豪; 藤田 達也
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - Frontiers of Research and Education with STACY (1) Initiatives for Human Resource Development
Tatsuya Fujita
日本原子力学会2025年秋の大会, Japanese, Keynote oral presentation
Sep. 2025 - Improvement of how to evaluate background cross sections on FRENDY-V2/GENESIS
Tatsuya Fujita; Go Chiba; Jun-Shuang Fan
日本原子力学会2025年秋の大会, Japanese, Oral presentation
Sep. 2025 - 核データ処理コードFRENDYの使用経験
藤田 達也
放射線遮蔽設計法に係るワークショップ第14回, Japanese, Nominated symposium
Aug. 2025 - Verification and sensitivity investigation of FRENDY-V2/GENESIS for sodium-cooled fast reactor fuel assembly
Jun-Shuang Fan; Tatsuya Fujita; Go Chiba
日本原子力学会2025年春の年会, English, Oral presentation
Mar. 2025 - Preliminary investigation to apply FRENDY-V2/GENESIS on three-dimensional LWR system
Tatsuya Fujita; Go Chiba
日本原子力学会2025年春の年会, Japanese, Oral presentation
Mar. 2025 - Development of Depletion Calculation Module on FRENDY-V2/GENESIS
Tatsuya Fujita; Go Chiba
日本原子力学会 北海道支部 第42回研究発表会, Japanese, Oral presentation
Mar. 2025 - Influence of implicit effect for multi-group cross-section perturbation on random-sampling-based uncertainty propagation
Fujita Tatsuya
日本原子力学会2024年秋の大会, Japanese, Oral presentation
Sep. 2024, 仙台, Japan, Past studies have mentioned that the treatment of implicit effect for cross-section perturbation affects the sensitivity coefficients and then the uncertainty propagation for neutronics parameters. The several approaches to consider the implicit effect have also been discussed for the random-sampling-based uncertainty propagation. In this study, continued from the presentation in the AESJ 2024 spring meeting, the influence of implicit effect for multi-group cross-section perturbation on random-sampling-based uncertainty propagation was evaluated for the k-infinity uncertainty in the multi-group neutron transport calculation. While the influence of the implicit effect was small on the UO$_{2}$ fuel pin-cell geometry, large influence was observed in the MOX fuel pin-cell geometry. However, it was considered that this influence could be reduced by refining the number of energy groups in neutron transport calculation and cross-section covariance matrix., [Domestic Conference] - Rolling of the reactor physics road map (RM2017)
Ushio Tadashi; Aizawa Naoto; Fujita Tatsuya; Gunji Satoshi
日本原子力学会2024年春の年会, Japanese, Invited oral presentation
Mar. 2024, 東大阪, Japan, The reactor physics road map is and has to remain "the guide for reactor physics engineers/researchers in considering future directions of technology and research developments," thus the periodical rolling by reactor physics engineers/researchers is necessary. In consideration of the fact that five years have already passed since the current 2017 version (RM2017, October 2017) was developed, and the environment surrounding nuclear energy has significantly changed such as the developments of GX (Green Transformation) strategy and Carbon-Neutrality by 2050, a new 2024 version (RM2024) was developed by revising RM2017 through the review of current items and descriptions. In the planning lecture by the reactor physics division, the details of this rolling work are introduced, and the expectations for the road map, the requirements for ideal road map, the desirable items, etc. are discussed by an exchange of opinions with reactor physics engineers/researchers., [Domestic Conference] - Preliminary study of multi-group cross-section perturbation on random-sampling-based uncertainty analysis
Fujita Tatsuya
日本原子力学会2024年春の年会, Japanese, Oral presentation
Mar. 2024, 東大阪, Japan, Past studies have mentioned that the treatment of implicit effect for cross-section perturbation affects the sensitivity coefficients and then the uncertainty analysis results for the k-infinity. The several approaches to consider the above implicit effect has also been discussed for the random-sampling-based uncertainty analysis. In this study, the influence due to implicit effect on typical nuclides and nuclear reactions in PWR 17$\times$17 UO$_{2}$ and MOX fuel assemblies was confirmed prior to treat the implicit effect on the random-sampling-based uncertainty analysis in future studies. In the UO$_{2}$ fuel assembly, the influence due to implicit effect on the k-infinity was small, thus the uncertainty quantification only considering the explicit effect would be applicable. On the other hand, further discussion about the influence due to implicit effect was necessary for the MOX fuel assembly., [Domestic Conference] - Status of nuclear data library in nuclear regulation
Fujita Tatsuya
日本原子力学会シグマ調査専門委員"将来の核データ"ワークショップ「原子炉と規制」, Japanese, Invited oral presentation
Dec. 2023, online, Japan, Based on publicly available information, recent discussions on the nuclear regulation and future outlook are presented. In addition, the following issues are raised for motivating the advancement of domestic nuclear data libraries. (1) Is there a formal documents including useful information and data for helping licensees holding their application accountable?, (2) Is there extensive support for nuclear constant libraries?, (3) What would be beneficial from verification and validation, and quality assurance perspective for licensess to adopt a new nuclear data library?, (4) What nuclear data of nuclides/reactions will we be working on? (What are the needs of the licensees?), (5) What future efforts are needed to quantify uncertainties caused by nuclear data libraries?, [Domestic Conference] - Discrepancy of Calculation Results Due to Treatment of Manufacturing Uncertainties in Fuel Assembly Geometry
Tatsuya Fujita
日本原子力学会2022年秋の大会, Japanese, Oral presentation
Sep. 2022 - Heterogeneous Cross Section Reproduction Method for Three-Dimensional Transient Analysis Code (2) An Unified Treatment for Heterogeneous Cross Sections of Same Material Regions within a Fuel Assembly Geometry
Tatsuya Fujita
日本原子力学会2022年春の年会, Japanese, Oral presentation
Mar. 2022 - Cross Section Reproduction Method for Three-Dimensional Heterogeneous Transient Analysis Code (1) Basic Study on Fuel Pin-Cell Geometry Problem
Tatsuya Fujita
日本原子力学会2021年秋の大会, Japanese, Oral presentation
Sep. 2021 - Development of Three-Dimensional Heterogeneous Transient Calculation Code RYUHO (1) Benchmark Calculation Results by Prototype Code and Future Development Works
Tatsuya Fujita; Naofumi Tsukamoto
日本原子力学会2021年春の年会, Japanese, Oral presentation
Mar. 2021 - Study on Calculatoin Cost Reduction for Random-Sampling-Based Uncertainty Quantification Using Multi-Level Monte Carlo Method (1) Applicability to Fuel Assembly Geometries
Tatsuya Fujita; Tomohiro Sakai
日本原子力学会2020年秋の大会, Japanese, Oral presentation
Sep. 2020 - Uncertainty Analysis on Depletion Calculation Using CASMO5 (2) Calculation Results in Fuel Assembly Geometry
Tatsuya Fujita; Tomohiro Sakai
日本原子力学会2020年春の年会, Japanese, Oral presentation
Mar. 2020 - CASMO5を用いた燃焼計算における不確かさ評価（1）燃料棒格子体系における評価結果
藤田 達也; 酒井 友宏
日本原子力学会2019年秋の大会, Japanese, Oral presentation
Sep. 2019 - CASMO5/SIMULATE5を用いたBEAVRSベンチマークの解析（2）サイクル2の解析結果
藤田 達也; 酒井 友宏
日本原子力学会2019年春の年会, Japanese, Oral presentation
Mar. 2019 - CASMO5/SIMULATE5を用いたBEAVRSベンチマークの解析（1）サイクル1の解析結果
藤田 達也; 酒井 友宏
日本原子力学会2018年秋の大会, Japanese, Oral presentation
Sep. 2018 - JENDL-4.0共分散データに基づくCASMO5/SIMULATE-5を用いた不確かさ評価（2）UAMベンチマーク問題（Phase Iにおける炉心体系）の解析
藤田 達也; 酒井 友宏
日本原子力学会2018年春の年会, Japanese, Oral presentation
Mar. 2018 - JENDL-4.0に基づくCASMO5/TRACE/PARCSを用いたSPERT-III実験解析・不確かさ評価
藤田 達也; 酒井 友宏
第6回炉物理専門研究会（KURRI-EKR-19）, Japanese, Oral presentation
Dec. 2017 - 3次元核熱結合解析コードTRACE/PARCSの検証及び妥当性確認（3）TRACE/PARCSを用いたSPERT-III実験の解析（冷温零出力・高温待機・高温全出力条件）
藤田 達也; 酒井 友宏
日本原子力学会2017年秋の大会, Japanese, Oral presentation
Sep. 2017 - JENDL-4.0の共分散データを用いたCASMO5/SIMULATE-5の不確かさ評価（1）UAMベンチマーク問題（Phase Iにおける集合体体系）の解析
藤田 達也; 岩橋 大希; 酒井 友宏
日本原子力学会2017年春の年会, Japanese, Oral presentation
Mar. 2017 - 3次元核熱結合解析コードTRACE/PARCSの検証及び妥当性確認（2）TRACE/PARCSを用いたSPERT-III実験の解析(高温零出力条件)
藤田 達也; 酒井 友宏; 岩橋 大希
日本原子力学会2016年秋の大会, Japanese, Oral presentation
Sep. 2016 - 燃料棒単位BWR炉心計算におけるスペクトル干渉効果の補正（3）群縮約誤差低減手法との結合
藤田 達也; 遠藤 知弘; 山本 章夫
日本原子力学会2014年春の年会, Japanese, Oral presentation
Mar. 2014 - 燃料棒単位BWR炉心計算におけるスペクトル干渉効果の補正（2）Leakage Indexの結合係数のテーブル化手法の改良
藤田 達也; 遠藤 知弘; 山本 章夫
日本原子力学会2013年春の年会, Japanese, Oral presentation
Mar. 2013 - 燃料棒単位BWR炉心計算におけるスペクトル干渉効果の補正
藤田 達也; 遠藤 知弘; 山本 章夫
日本原子力学会2012年秋の大会, Japanese, Oral presentation
Sep. 2012 - 逐次網羅的探索手法による燃料棒単位詳細メッシュBWR炉心核計算に適したエネルギー群構造の決定と評価
藤田 達也; 多田 健一; 遠藤 知弘; 山本 章夫; 小坂 進矢; 平野 豪; 野崎 謙一朗
日本原子力学会2011年秋の大会, Japanese, Oral presentation
Sep. 2011 - 燃料棒単位詳細メッシュBWR炉心核計算に適したエネルギー群構造の逐次網羅的探索手法の検討
藤田 達也; 多田 健一; 遠藤 知弘; 山本 章夫; 小坂 進矢; 平野 豪; 野崎 謙一朗
日本原子力学会2011年春の年会, Japanese, Oral presentation
Mar. 2011 - BWRにおけるサブチャンネル相当熱水力解析手法の検討
多田 健一; 藤田 達也; 遠藤 知弘; 山本 章夫; 小坂 進矢; 平野 豪; 野﨑 謙一朗
日本原子力学会2010年秋の大会, Japanese, Oral presentation
Sep. 2010 - BWR体系における燃料棒単位詳細メッシュ炉心核計算手法のエネルギー群構造の検討
藤田 達也; 大塚 一将; 多田 健一; 遠藤 知弘; 山本 章夫; 小坂 進矢; 平野 豪
日本原子力学会2010年秋の大会, Japanese, Oral presentation
Sep. 2010 - 燃料棒単位核定数の合成における燃焼度の取り扱いの検討
藤田 達也; 多田 健一; 山本 章夫; 山根 義宏; 小坂 進矢; 平野 豪
日本原子力学会2010年春の年会, Japanese, Oral presentation
Mar. 2010 - 「常陽」関連施設を用いた学生実習プログラム（3）原子炉シミュレータ実験に参加して
藤田 達也; 山根 義宏; 青山 卓史
日本原子力学会2009年春の年会, Japanese, Invited oral presentation
Mar. 2009 - Pin-by-pin体系におけるBWR燃料核定数の作成手法の検討
藤田 達也; 多田 健一; 山本 章夫; 山根 義宏
日本原子力学会 中部支部 研究発表会, Japanese, Oral presentation
Dec. 2008
■ Research Themes
- 臨界実験を用いたデータ同化手法の実用化に資する次元削減スキームの構築
科学研究費助成事業
01 Apr. 2025 - 31 Mar. 2029
藤田 達也
日本学術振興会, 基盤研究(C), 国立研究開発法人日本原子力研究開発機構, 25K08533
Others
- Jul. 2025 - Present
日本原子力学会炉物理部会「SNS活用検討タスクチーム」
タスクチームメンバー - Apr. 2025 - Present
日本原子力学会北海道支部役員
2025.4～現在 幹事（会計） - Apr. 2025 - Present
日本原子力学会核データ部会運営小委員
2025.4～現在 企画担当 - Apr. 2025 - Present
日本原子力学会プログラム編成ワーキンググループ
WGメンバー
2025年秋の大会：部会別専門分野リーダー - Apr. 2025 - Present
日本原子力学会炉物理部会運営小委員
2025.4-2027.3：財務小委員会担当幹事 - Nov. 2024 - Present
JENDL委員会 リアクタ積分WG
専門委員 - Oct. 2024 - Mar. 2025
日本原子力学会炉物理部会「炉物理部会の役割検討」ワーキンググループ
WG委員 - 日本原子力学会炉物理部会「炉物理ロードマップ調査・検討」ワーキンググループ
原子炉物理分野の研究開発ロードマップ 2017 年版
オブザーバ - Covariance Data Utilization and Promotion WG in JENDL Committee
Observer - OECD/NEA/NSC LWR-UAM Benchmark Project Phase I
One of contributors to submit results
