論文

• HISASHI NINOKATA. On Void Reactivity Limitation for the Core Loaded with Mixed Nitride Fuels, Journal of Nuclear Science and Technology, Vol. 46, No. 10, pp. 981-994, Oct. 2010.
• HISASHI NINOKATA. Proper Orthogonal Decomposition of the Flow in Geometry Containing a Narrow Gap, Journal of Theoretical and Computational Fluid Dynamics, Springer Link, Vol. 23, No. 5, pp. 333-351, Sept. 2009.
• HISASHI NINOKATA. Analysis of low Reynolds number turbulent flow phenomena in nuclear fuel pin subassemblies of tight lattice configuration, Nuclear Engineering and Design, Vol. 239, No. 5, pp. 855-866, May 2009.
• G. Sorokin, H. Ninokata, A. Sorokin, H. Endo, E. F. Ivanov. Experimental and Numerical Study of Liquid Metal Boiling in a System of Parallel Bundles under Natural Circulation Conditions, Journal of Nuclear Science and Technology, Vol. 43, No. 6, pp. 623-634, June 2006.
• H. Ninokata. A Comparative Overview of Thermal Hydraulic Characteristics of Integrated Primary System Nuclear Reactors, Journal of Nuclear Engineering and Technology, Vol. 38, No. 1, pp. 33-44, Feb. 2006.
• E. Baglietto, H. Ninokata. Anisotropic Eddy Viscosity Modeling for Application to Industrial Engineering Internal Flows, Int. J. Transport Phenomena, Vol. 8, No. 2, 2006.
• E. Baglietto, H. Ninokata, T. Misawa. CFD and DNS Methodologies Development for Fuel Bundle Simulations, Nuclear Engineering and Design, Vol. 236, pp. 1503-1510, 2006.
• S. Wang, H. Ninokata. A Three-Dimensional DSMC Simulation of Single-Stage Turbomolecular Pump Adopting Accurate Intermolecular Collision Models, Journal of Fluid Science and Technology, Vol. 1, No. 2, pp. 58-71, 2006.
• H. Ninokata. Direct Numerical Simulation of Turbulent Flows in a Subchannel of Tight Lattice Fuel Pin Bundles of Nuclear Reactors, Annual Report of the Earth Simulator Center, No. 12, pp. 293, Dec. 2005.
• E. Baglietto, H. Ninokata. A turbulence model study for simulating tight lattice rod bundles, Nuclear Engineering and Design, Vol. 235, No. 7, pp. 773-784, July 2005.
• Y. Mizuno, H. Ninokata, D.J. Finnicum. Risk-informed design of IRIS using a level-1 probabilistic risk assessment from its conceptual design phase, Reliability Engineering and System Safety, Vol. 87, pp. 201-209, June 2005.
• 湊明彦, 二ノ方寿, 越塚誠一, 三澤雅樹. 二相流複雑流動解析技術による厚肉多孔板のCCFL実験解析 (L31), 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. 317, 2004.
• A. Minato, T. Nagayoshi, M. Misawa, A. Suzuki, H. Ninokata, S. Koshizuka. Numerical Simulation Method of Complex 3D Gas-Liquid Two-Phase Flow, ICMF2004 Yokohama,Japan, 2004.
• M. Carelli, L. Conway, L. Oriani, B. Petrovic, C.Lombardi, M. Ricotti, A. Barroso, J.Collado, L Cinotti, N. Todreas, D. Grgic, M. Moraes, H. Ninokata, et al.. The Design and Safety Features of the IRIS Reactor, Nucl. Eng. Design, Vol. 230, pp. 151-167, 2004.
• H. Ninokata. CFD and CMFD applications for subchannel analysis of fuel rod bundles (Keynote Paper), Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety October 4-8, Nara, Japan, pp. KN-12, 2004.
• T. Misawa, H. Ninokata, I.Maekawa. Calculation of Detailed Velocity Distributions in Fuel Pin Bundles of Infinite Triangular Array Configuration Using Direct Numerical Simulation, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-377, 2004.
• E. Baglietto, H. Ninokata. CFD Modeling of Secondary Flows in Fuel Rod Bundles, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-343, 2004.
• V. Kriventsev, H. Ohshima, A. Yamaguchi, H. Ninokata. Turbulence Modeling and Pressure Drop Prediction in Channel Flows, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-032, 2004.
• T. Ishizu, H. Endo, H. Ninokata. On the Design Limit of the Void Reactivity for MOX-Fueled LMFR Core, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-371, 2004.
• A.P. Sorokin, H. Ninokata, G.P. Bogoslovskaya, A.V. Zhukov. Models and Characteristics of Interchannel Exchange as a Decisive Factor in Subchannel Analysis of Reactor Subassembly, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-086, 2004.
• H. Ninokata, M. Sadatomi, T. Okawa, A. Serizawa, K. Mishima, S. Koshizuka, A. Tomiyama, Y. Yamamoto, Y. Kudo, A. Hotta, K. Nishida, N. Shirakawa. Current Status of Generalized Boiling Transition Model Development Applicable to a Wide Variety of Fuel Bundle Geometry, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-363, 2004.
• H. Shirai, A. Hotta, H. Ninokata. A strategy of Implementation of the Improved Constitutive Equations for the Advanced Subchannel Code, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-384, 2004.
• A. Hotta, H. Shirai, M. Azuma, M. Sadatomi, A. Kawahara, H. Ninokata. A Modified Equilibrium Void Distribution Model Applicable for Conventional Square and Tight Lattice BWR Fuel Bundles, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-088, 2004.
• M. Azuma, A. Hotta, H. Shirai, H. Ninokata. Effects of Fluid Properties on the Cross-Flow Between Subchannels, Proc. 6th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety (NUTHOS-6) October 4-8, Nara, Japan, pp. N6P-089, 2004.
• H. Ninokata. Two-phase flow modeling in the rod bundle subchannel analysis, Scientifique et technique de la Société Hydrotechnique de France, Progrès récents des méthodologies de modélisation des écoulements diphasiques, IAHR-SHF2004 Lyon, France, 2004.
• S. Wang, H. Ninokata. Influences of Geometrical Properties to the Pumping Characteristics of Turbo Molecular Pump by DSMC Calculation, Proc 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety,NTHAS-086, Sapporo, Japan , 2004.
• E. Baglietto, H. Ninokata. Simulation of Turbulent Flow Inside Tight Lattice Bundles with an Improved Non-Linear Eddy Viscosity Model, Proc 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, NTHAS-059, Sapporo, Japan , 2004.
• J. Kaneko, A. Minato, H. Ninokata. Multi-dimensional analysis of two-phase flow inside subchannels of nuclear fuel assembly, Japan-US Seminar on Two-Phase Flow Dynamics, Nagahama, Vol. 1, pp. 327-333, 2004.
• J. Kaneko, H. Ninokata. Study on the redistribution of flow due to cross flow between subchannels, 1st COE-INES International Symposium INES-1 Tokyo, Japan, pp. Paper No.75, 2004.
• T. Yokoyama, T. Fujiki, H. Endo, H. Ninokata. A study on reactivity insertion controlled LMR cores with metallic fuel, 1st COE-INES International Symposium INES-1, Tokyo, Japan, pp. Paper No. 80, 2004.
• T. Ishizu, H. Endo, M. Tokiwai, T. Yokoyama, H. Ninokata. Study of self-controllability and self-terminability of the core loaded with high thermal conductivity fuels, 1st COE-INES International Symposium INES-1, Tokyo, Japan, pp. Paper No. 91, 2004.
• Y. Kumagai, H. Ninokata. The preliminary IRIS PRA-Based Seismic Margins Assessment, 1st COE-INES International Symposium INES-1, Tokyo, Japan, pp. Paper No. 116, 2004.
• S. Wang, H. Ninokata. The Pumping Performances of the Turbo Molecular Pump Simulated By Direct Simulation Monte Carlo Method, 1st COE-INES International Symposium INES-1, Tokyo, Japan, pp. Paper No. 111, 2004.
• E. Baglietto, H. Ninokata. CFD Modeling of Flow in Geometrically Disturbed Rod Bundles, International Journal of Heat and Technology, Vol. 22, No. 2, 2004.
• 二ノ方寿, 中田耕太郎. 原子力プラントにおける火災や燃焼化学反応を伴う熱流動問題研究専門委員会報告（1）はじめに, 日本原子力学会　２００４年春の年会要旨集　, Vol. II, pp. (1), 2004.
• H. Ninokata. RANS and DNS: Improved Turbulence Modeling for Single-Phase Flow Rod Bundle Applications, ICONE12 CFD Seminar, Crystal City, USA, 2004.
• 張敏燕, 堀田亮年, 白井浩嗣, 二ノ方寿. サブチャンネル間気泡移動に対する物性因子の影響 (L-48), 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. 334, 2004.
• 堀田亮年, 白井浩嗣, 佐田富道雄, 川原顕磨呂, 二ノ方寿. 平衡ボイド分布モデル改良の方向性 (L-49), 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. 335, 2004.
• 小池芳春, 二ノ方寿, 小倉克規, 水野祐子. IRISプラントPSAにおける炉心損傷頻度評価 (M-46), 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. 389, 2004.
• 堀田亮年, 白井浩嗣, 佐田富道雄, 川原顕磨呂, 二ノ方寿. 二次元流路網理論に基づく燃料バンドル二相クロスフローモデルの改良, 日本機械学会：2004年次大会、北海道大学、2004年9月7日, 2004.
• 二ノ方　寿. 液体金属冷却高速炉の意義と研究開発　－21世紀の地球環境とエネルギー対策への貢献－, 日本原子力学会北海道支部講演会2004年11月29日, 2004.
• 山本雄一, 白川典幸, 堀江英樹, 山本泰, 大川富雄, 越塚誠一, 二ノ方壽. TF-MPSによるスペーサー周りの液滴挙動の解析 (L-51), 日本原子力学会　２００４年春の年会要旨集 , Vol. II, pp. 337, 2004.
• T. Misawa, I. Maekawa, H. Ninokata. Calculation of Heat Transfer Coefficients on a Flat Plate by Pseudo Direct Numerical Simulation of Turbulence, Journal of Science and Technology, Vol. 40, No. 10, pp. 703-707, 2003.
• 仲嶺信英, 堀池寛, 片岡勲, 二ノ方壽, 宮崎慶次. 高速増殖原型炉「もんじゅ」控訴審判判決に係わる原子力安全の技術的論点, 日本原子力学会誌, Vol. 45, No. 8, 2003.
• E. Baglietto, H. Ninokata. Selection of an Appropriate Turbulence Model to Evaluate Performances of Novel Fuel Geometries for the IRIS Reactor, Proc. 4th ASME-JSME Joint Fluids Engineering Conference on CD-ROM, 2003.
• A.Hotta, T.Anegawa, h.Ninokata. Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTREE, Nuclear Technology, Vol. 42, No. 3, pp. 205-229, 2003.
• N. Doda, Y. Okano, H. Ninokata. Numerical Simulation of Sodium Pool Fire, Nuclear Technology, Vol. 144, No. 2, pp. 175-185, 2003.
• 金子順一, 二ノ方壽, 湊明彦. 二流体モデルによるサブチャンネル体系内気液二相流の三次元解析, 日本原子力学会　2003年秋の大会予稿集, pp. F-40, 393, 2003.
• 三沢丈冶, 二ノ方壽, 前川勇, 赤松幹夫. 擬似直接数値計算法のサブチャンネル内乱流解析への応用（2）無限三角配列バンドル解析, 日本原子力学会　2003年秋の大会予稿集, pp. F-41, 394, 2003.
• 三沢丈冶, 前川勇, 二ノ方壽. 擬似直接数値計算法のサブチャンネル内乱流解析への応用；境界適合格子系差分スキームにおける適応性の検証, 日本原子力学会　2003年春の年会要旨集, pp. J-19, 445, 2003.
• 山田静夫, 二ノ方壽. サブチャンネル解析を用いた稠密バンドル体系における境界熱流束の予測, 日本原子力学会　2003年春の年会要旨集, pp. J-20, 446, 2003.
• 佐藤浩, 二ノ方壽, 遠藤寛. 水素製造高速炉の安定性, 日本原子力学会　2003年春の年会要旨集, pp. L-53, 582, 2003.
• 常盤井守泰, 福島公親, 横山次男, 遠藤寛, 二ノ方壽. 金属燃料の水冷却炉への適用可能性, 日本原子力学会　2003年秋の大会予稿集, pp. E-7-10, 286-289, 2003.
• G. Sorokin, H. Ninokata, A. Sorokin. Development of Thermohydraulic Codes For Modekung Liquid Metal Boiling In Reactor Fuel Subassenblies, 日本原子力学会　2003年秋の大会予稿集, pp. F-2, 355, 2003.
• 白川典幸, 堀江英樹, 三島嘉一郎, 二ノ方壽. TF-MPS法による流動様式の解析, 日本原子力学会　2003年秋の大会予稿集, pp. F-38, 391, 2003.
• M. Tokiwai, H. Endo, K. Fukushima, T. Yokotama, H. Ninokata. Feasibility of Metallic Fueled Light Water Reactor, Proc. GLOBAL2003-Adbanced Nuclear Energy and Fuel Cycle Systems (ANS/ENS) on CD-ROM, 2003.
• V. Kriventsev, H. Ohshima, A. Yamaguchi, H. Ninokata. Numerical Presiction of Secondary Flows in Complex Areas Using Concept of Local Turbulent Reynolds Number, Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 40, No. 9, pp. 655-663, 2003.
• M. D. Carelli, L. Oriani, L. Conway, C. Lambardi, A. Barroso, J. Collado, L. Cinnoti, M. Moraes, D. Grgic, H. Ninokata, D. Ingersoll, R. Borougbs. The Design and Safety Features of the IRIS Reactor, Proc. 11th International Conference on Nuclear Engineering (ICONE11), pp. 36564, 2003.
• H. Ninokata, M. Sadatomi, T. Okawa, S. Serizawa, K. Mishima, K. Yoshiro, A. Hotta, S. Morooka, Y. Yamamoto, N. Shirakawa, K. Nishida. Development of Generalized boiling Transition Model Applicable to Wide Variety of BWR-TYpe Fuel Bundle Geometry-Master Plan ans Status of First Year, Proc. 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), pp. A00307, 2003.
• Y. Kornienko, H. Ninokata. Sevelopment of Generalized Integral Form for Two-Phase Flow Quasi-One-Dimension Closure Relationships of Distribution Parameters and Wall Friction, Heat and Mass Transfer Coefficients for Pope, Annular and Subchannel Geometry, Proc. 10th International Topical Meetion on Nuclear Reactor Thermal Hydraulics (NURETH-10), pp. A00312, 2003.
• H. Ninokata. A Comparative Overview of Thermal Hydraulic Characteristics of Integrated Primary System Nuclear Reactors, Proc. 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), pp. KL-07, 2003.
• T. Misawa, H. Ninokata, I. Maekawa. Calculation of Detailed Velocity and Temperature Distributions in a Triangular Pin Bundle Using Pseudo Direct Numerical Simulation, Proc. 10th International Topical Meeting on Nuclear Peactor Thermal Hydraulics (NURETH-10), pp. E00218, 2003.
• E. Baglietto, H. Ninokata. Turbulence Models Evaluation for Heat transfer Simulation in Tight Lattice Fuel Bundles, Proc. 10th International Topical Meeting on Nuclear Peactor Thermal Hydraulics (NURETH-10), pp. E00214, 2003.
• H. Ninokata, M. Sadatomi, T. Okawa, A. Serizawa, K. Mishima, S. Koshizuka, K. Yoshiro, A. Hotta, S. Morooka, Y. Yamamoto, N. Shirakawa, K. Nishida. Development of Generalized Boiling transition Model Applicable for Wide Variety of Fuel Bundle Geometries, Proc. International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), pp. 1013, 2003.
• 白井浩嗣, 堀田亮年, 張敏燕, 二ノ方壽. VOF法によるサブチャンネル間気泡移動数値解析, 日本原子力学会　2003年秋の大会予稿集, pp. F-39, 392, 2003.
• Y. Mizuno, H. Ninokata. Preliminary Level-1 Probabilistic Risk Assessment of the IRIS Plant in a Conceptual and Prelimary Design Phase, Proc. International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP2003), pp. 1078, 2003.
• E. Baglietto, H. Ninokata. Selection of an Appropriate Turbulence Modeling in a CFD code for an Ultra-long Life Core for the IRIS Reactor, Proc. International Conference on Global Environment and Advanced Nuclear Power Plant (GENES4/ANP2003), pp. 1153, 2003.
• N. Doda, Y. Okano, H. NInokata. Numerical SImulation of Sodium Pool Fire, Nuclear Technology, Vol. 144, No. 2, pp. 175-185, 2003.
• 湊明彦, 二ノ方壽, 越塚誠一, 三澤雅樹. 原子炉における気液二相流複雑評価に関する技術開発, 日本原子力学会　2002年春の年会要旨集, pp. I-24, 444, 2002.
• 藤田朋子, 二ノ方壽, 遠藤寛. 窒素物燃焼炉心のボイド反応度制限, 日本原子力学会　2002年秋の大会予稿集, pp. K-41, 324, 2002.
• E. Baglietto, H. Ninokata. Assessment of Steam Generator Overheationg Tube Failure Postulated in FBR Plant using RELAP 5, 日本原子力学会　2002年秋の大会予稿集, pp. L-24, 349, 2002.
• B. Vladimir, H. Ninokata, H. Endo. Comparative Assessment of Different Calculation Methods Applied to the Highly Degraded FBR Cores, 日本原子力学会　2002年秋の大会予稿集, pp. M-47, 423, 2002.
• 佐藤浩, 二ノ方壽, 遠藤寛. 多目的高速炉を用いた水素製造の負荷変動時安定化, 日本原子力学会　2002年秋の大会予稿集, pp. K-42, 325, 2002.
• 白井浩嗣, 堀田亮年, 原貴, 二ノ方壽. 燃料ピン出力分布変化を考慮したタービントリップ試験条件におけるBWR燃料集合体内詳細ボイド分布解析, 日本原子力学会　2002年秋の大会予稿集, pp. L-38,363, 2002.
• 三沢丈冶, 二ノ方壽, 前川勇. 乱流擬似直接数値シミュレーションによる平行平板熱伝導率の計算, 日本原子力学会　2002年秋の大会予稿集, pp. L-29, 354, 2002.
• V. Barchevtsev, H. Ninokata, V. Artisyuk. Potential to approach the long life core in a light water reactor with uranium oxide fuel, Annals of Nuclear Energy, Vol. 29, pp. 595-608, 2002.
• V. Kriventsev, H. Ohshima, A. Yamaguchi, H. Ninokata. Numerical prediction of secondary flows in complex areas using concept of local turbulent Reynolds number, Proc. 10th International Conference on Nuclear Engineering (ICONE10) on CD-ROM,, 2002.
• Y. Mizuno, K. Ogura, L. Conway, H. Ninokata. Preliminary Probabilistic Safety Assessment of the IRIS PlantICONE10-22095, Proc. 10th International Conference on Nuclear Engineering (ICONE10) on CD-ROM, 2002.
• M.D. Carelli, K. Miller, C. Lombardi, N. Todreas, E. Greenspan, H. Ninokata, F. Lopez, et al.. IRIS: Proceeding toward the preliminary design, Proc. 10th International Conference on Nuclear Engineering (ICONE10) on CD-ROM, 2002.
• V. Barchevtsev, V. Artisyuk, H. Ninokata. Concept of erbium dopted uranium oxide fuel cycle in light water reactors, Nuclear Science and Technology, Vol. 39, No. 5, pp. 506-513, 2002.
• V. Kriventsev, A. Yamaguchi, H. Ninokata. Multi-scale viscosity model of turbulence, Advances in Fluid Modeling and Turbulence Measurements, World Scientific Publishing Co., Pte. Ltd, pp. 577-584, 2002.
• V. Barchevtsev, V. Artisyuk, H. Ninokata. Double-strata high burnup fuel performance in LWRs, Annals of Nuclear Energy, Vol. 29, pp. 1919-1932, 2002.
• V. Barchevtsev, V. Artisyuk, H. Ninokata. Synergetic potential of light water reactors, Proc. Embedded Topical Meeting at the 2002 ANS Annual Meeting, 2002.
• K. Ogura, H. Ninokata. A robust approach to uncertainty in nuclear reactor thermal-hydraulic analysis, Proc. 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3, pp. 93-98, 2002.
• T. Misawa, I, Maekawa, H. Ninokata. Calculation of Heat Transfer Coefficients on a Flat Plate by Pseudo Direct Numerical Simulation of Turbulence, Proc. 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3), pp. 116-120, 2002.
• T. Fujita, H. Endo, H. Ninokata. On void reacitity limitation for nitride-fueled LMFR core, Proc. 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3, pp. 600-607, 2002.
• H. Shirai, H. Ninokata, A. Hotta, T. Hara. Analytical study on detailed void distributions inside BWR fuel bundle under turbine trip event considering realistic pin power distribution, Proc. 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3, pp. 500-507, 2002.
• E. Baglietto, H. Ninokata. Study of steam generator overheating tube failure in FBRs, Proc. 3rd Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS3), pp. 616-622, 2002.
• H. Ninokata, Y. Hizume, H. Endo, T. Sawada. Evaluation of self-controllability of LMFBRs against ATWS, Progress in Nuclear Energy, Vol. 40, No. 3-4, pp. 569-575, 2002.
• K. Ogura, H. Ninokata. An Approach of Uncertainty Evaluation for Thermal-Hydraulics Analysis, Proc. 10th International Conference on Nuclear Engineering (ICONE10) on CD-ROM, 2002.
• A.Hotta, M.Zhang, H.Ninokata. BWR Regional Instability Analysis by TRAC/BF1-ENTREE-Ⅱ:Application to Ringhals Unit 1 Stability Test-, Nucl Technolgy, No. 135, pp. 17-38, 2001.
• H.Kuraishi, T.Sawada, H.Endo, H.Ninokata. Inherent and Passive Safety Sodium-Cooled Fast Reactor Core Design with Minor Actinide and Fission Product Incineration, Nuclear Science and Engineering, Vol. 138, pp. 205-232, 2001.
• N. Doda, H. Ninokata, H. Ohira. Prediction of Release Rate of Burnt Sodium as Aerosol, Journal of Nuclear Science and Technology, Vol. 38, No. 1, 2001.
• M. D. Carelli, D. V. Paramonov, K. Miller, C. V. Lombardi, M. E. Ricotti, N.E. Todreas, E. Greenspan, K. Yamamoto, A. Nagano, H. Ninokata, J. Robertson, F. O. IRIS Reactor Development, on CD-ROM,Proc. 9th International Conference on Nuclear Reactor, 2001.
• Y. Kornienko, E. Kornienko, H. Ninokata. On closure strategy for 1D thermohydraulics models and closure relationships of two-phase flows in simple and subchannel geometry for NPP accident conditions , Proc. 9th International Conference on Nuclear Engineering (ICONE9)on CD-ROM, 2001.
• V. Kriventsev, H. Ninokata, A. Yamaguchi. Multi-scale viscosity model of turbulence for fully-developed channel flows, Proc. 9th International Conference on Nuclear Engineering (ICONE9)on CD-ROM, 2001.
• V. Barchevtsev, V. Artisyuk, H. Ninokata. Double-strata high burnup fuel performance in LWRs, Proc. ANS 2001 Winter Meeting, 2001.
• A. Netchaev, H. Endo, T. Sawada, H. Ninokata. The concept and neutronic characteristic of a multipurpose fast reactor, Annals of Nuclear Energy, Vol. 28, pp. 1083-1099, 2001.
• H. Shirai, H. Ninokata. Prediction of the Equilibrium Two-Phase Flow Distributions in Inter-Connected Subchannel Systems, Journal of Nuclear Science and Technology, Vol. 38, No. 6, pp. 379-387, 2001.
• V. Kriventsev, H. Ninokata, A. Yamaguchi. Numerical accuracy of temperture, velocity and pressure distributions predicted with efficient finite-differencing (EFD) scheme,CHT'01, Advanced in Computational Heat Transfer, Vol. Ⅱ, pp. ４６９－４７６, 2001.
• A. Romano, V. Kriventsev, H. Ninokata, N.E. Todreas. Novel fuel geometries for the generation IV IRIS reactor, on CD-ROM, Proc. 9th International Conference on Nuclear Engineering(ICONE9) , 2001.
• A.Hotta, M.Zhang, H.Ninokata. BWR Regional Instability Analysis by TRAC/BF1-ENTREE-I:Application to Density-wave Oscillation-, Nucl Technolgy, No. 135, pp. 1-16, 2001.
• A.Hotta, H.Ninokata, A.J.Baratta. Development of Parallel Coupling System between Three Dimensional Nodal kinetic Code ENTREE and Two-Fluid Plant Simulator TRAC/BF1, Journal of Nuclear Science and Technology, Vol. 37, No. 10, pp. 840-854, 2000.
• A.Netchaev, T.Sawada, H.Ninokata, H.Endo. Long life Multipurpose Small Size Fast Reactor with Liquid Metallic-fueled Core, Progress in Nuclear Energy, Vol. 37, No. 1-4, pp. 299-306, 2000.
• F.Kasahara, H.Ninokata, A.P.Sorokin, G.P.Bogoslovskaya. Analysis of liquid-metal boiling under the natural circulation condition, Proc.2nd Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, pp. 45-52, 2000.
• H.Endo, A.Netchaev, K.Yoshimura, K.Arie, M.Yamadate, T.Sawada, H.Ninokata. A Concept of the Multipurpose Liquid Metallic-fueled Fast Reactor System(MPFR), Progress in Nuclear Energy, Vol. 37, No. 1-4, pp. 291-298, 2000.
• H. Endo, H. Ninokata, A. Netchaev, T. Sawada. Potential of Multi-Purpose Liquid Metallic Fueled Fast Reactor (NPFR) as A Hydrogen Production System, OECD/NEA First Information Exchange Meeting on Nuclear Production of Hydrogen, 2000.
• Hisashi Ninokata, Akitoshi Hotta, Hioyuki Takeuchi, Youjirou Suzawa. Regional instability evaluation of Ringhals unit 1 based on extended frequency domain model, Nuclear Engineeringa and Design, No. 200, pp. 201-220, 2000.
• Hisashi Ninokata, Fumio Kasahara. The multi-fluid multi-phase subchannel analysis code KAMUI for subassembly accident analysis of an LMFR, Journal of Nuclear Science and Technology, Vol. 37, No. 8, pp. 654-669, 2000.
• Hisashi Ninokata, Vladimir Kriventsev. Numerical method for simulation of fluid flow and heat transfer in geometrically disturbed rod bundles, Journal of Nuclear Science and Technology, Vol. 37, No. 8, pp. 646-653, 2000.
• H.Ninokata, V.Kriventsev. An effective finite-difference scheme for problems of turbulent heat and mass transfer, Nuclear Engineeringa and Design, No. 200, pp. 11-21, 2000.
• H.Ninokata, M.Aritomi, T.Anegawa, et al.. Development of the NASCA code for predicting transient bt phenomena in bwr bundles, proc,OECD-CSNI Workshop on Advanced Themal-Hydraulic and Neutronic Codes: Current and Future Applications, 2000.
• H.Ninokata, Y.Kornienko. Analytical Foundation and Appraisal of Wall Friction and Heat Transfer Coefficients used in the Bubble Detachment Region of Subcooled Boiling Flow, ( ICONE-8 8723 ) on CD ROM 8th International Conference on Nuclear Engineering, Vol. 8, No. 8723, 2000.
• H.Ninokata, A.P.Sorokin, P.L.Kirillov. Comparison of Sodium and Lead/Lead-Bismuth as a Coolant and LMFR Safety, Invited paper ( ICONE-8 8826 ) on CD ROM 8th International Conference on Nuclear Engineering, Vol. 8, No. 8826, 2000.
• H.Ninokata, M.D.Carelli, D.V.Paramonov, C.V.Lombardi, M.E.Ricotti, N.E.Todreas, E.Greenspan, J/Vujic, R.Yamazaki, K.Yamamoto, A.Nagano, G.L.Fiorini, P.Dumaz, T.Abram. IRIS International New Generation Reactor, ( ICONE-8 8447 ) on CD ROM 8th International Conference on Nuclear Engineering, Vol. 8, No. 8447, 2000.
• A.Netchaev, Y.Hizume, H.Endo, T.Sawada, H.Ninokata. Safety Charactereistics of the Multipurpose Fast Reactor (MPFR), Annals of Nuclear Energy, 2000.
• 二ノ方､村松､西村､富山 他. 原子炉熱流動の微視的シミュレーション, 日本原子力学会誌, Vol. 42, No. 12, pp. 1242-1259, 2000.
• Hisashi Ninokata, Akitoshi Hotta, Katsumi Tate. Nonlinear Iterative Nodal Method Applied to Neutron Flux Modal Analysis, Jounal of Nuclear Science and Technology, Vol. 36, No. 11, pp. 1009-1020, 1999.
• H.NINOKATA. An effective, locally exact finite-difference scheme for convection-diffusion problems, Numerical Heat Transfer, Part B, Vol. 36, No. 2, pp. 183-205, 1999.
• Hisashi Ninokata, Hiroshi Shirai. Calculation of two-phase flow distributions in subchannel systems by the principle of minimum entropy production, Thsermophysics99, pp. 9-11, 1999.
• HISASHI NINOKATA. Microscopic approaches in nuclear reactor thermal hydraulics compytations, (Keynote Lecture) Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9) on CD ROM, 1999.
• Hisashi Ninokata, Vladimir Kriventsev. Calculation of detailed velocity and temperature distributions in a rod bundle of nuclear reactor, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9) on CD ROM, 1999.
• Hisasi Ninokata, Hiroshi Shirai. Prediction of the equilibrium two-phase flow distribution in a rod bundle and void drift, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9) on CD ROM, 1999.
• Hisasi Ninokata, Norihiro Doda, Hiroaki Ohira. Prediction of release rate of burnt sodium as aerosol, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9) on CD ROM, 1999.
• Hisashi Ninokata, Fumio Kasahara. Development of multi-fluid multi-phase subchannel analysis code KAMUI for analyzing accident conditions in a subassembly of LMFR , Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9) on CD ROM, 1999.
• Hisashi Ninokata, Akitoshi Hotta, Anthony J.Baratta. Development of three dimensional kinetic code ENTREE coupled with TRAC-BF1, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics ( NURETH-9 ) on CD ROM, 1999.
• Hisashi Ninokata, Akitoshi Hotta, Anthony J.baratta. Development of three dimensional kinetic code ENTREE coupled with TRAC-BF1, Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics ( NURETH-9 ) on CD ROM, 1999.
• A.Hotta, H.Ninokata, A.J.Baratta. Peach Bottom 2 Turbine Trip Simulation by Coupling System of 3D Nodal Code ENTREE and TRAC-BF1, Int.Topical.Mtg.on Math.and Comp., pp. 1804, 1999.
• HISASHI NINOKATA. An algorithm for attenuation of turbulence in particulate How linked to the Fluid-dynamics Code COMMIX-M(共著), Journal of Nuclear Science and Technology, Vol. 35, No. 2, pp. 101-112, 1998.
• Ninokata, H., Sawada. Global Environment & Nuclear Energy Systems-2, Proceedings of the Second International Symposium GENES-2 ; Special Issue of Progress in Nuclear Energy Pergamon Press, Vol. 32, Number 3/4, pp. 0149-1970, 1998.
• H.Ninokata, G.P.Bogoslovskaya, S.Cevolani, A.A.Rinejski, A.P.Sorokin, A.V.Zhukov. LMFR core and heat exchanger thermohydraulic design: Former USSR and present Russian approaches, International Atomic Energy Agency, Vol. 1060, pp. 1011-4289, 1998.
• HISASHI NINOKATA. Ageneral method to evaluate passive safety characteristics of FBRs, Proc. 5-th International Topical Meeting on Nuclear Thermal Hydraulics, Operations & Safety(NUTHOS-5), 1997.
• V. Kriventsev, H. Ninokata. An effective finite-difference scheme for transient problems of heat and mass transfer(共著), Proc. 8th Topical Meeting on Nuclear Reactor Thermal Hydraulics(NURETH8), 1997.
• HISASHI NINOKATA. Evaluation of FCI under severe core accident conditions in fast breeder reactors, Proc. 5-th Int. Topical Meeting on Nuclear Thermal Hydraulics, OPerations and Safety(NUTHOS-5), 1997.
• HISASHI NINOKATA. Acceleration of the outer iterations of the space-dependent neutron kinetics equations solution, Annals of Nuclear Energy, Vol. 23, No. 17, pp. 1407-1424, 1996.
• HISASHI NINOKATA. Validation studies on a Computational model for moiten materials freezing, Nuclear Technology, Vol. 113, No. 2, pp. 167-176, 1996.
• HISASHI NINOKATA. Development of thermohydranlics computer program for thermal striping phenomena, Nuclear Technology, Vol. 113, No. 1, pp. 54-72, 1996.
• HISASHI NINOKATA. Benchmark exercise for multi-dimensional thermohydraulic analysis codes-Buoyancy driven penetration flow phenomena and thermal stratification-, Journal of Hydraulic Research, Vol. 34, No. 3, pp. 317-344, 1996.
• HISASHI NINOKATA. Calculation of a materials relocation experiement simulation a care disruptive accident condition in fast breeder reactors, Nuclear Engineering and Design, Vol. 157, pp. 177-196, 1995.
• HISASHI NINOKATA. Analysis of two-phase flow inter-subchannel mass and momentum exchanges by the two-fluid model approach, Proc.7th International Topical Meetingon Nuclear Reactor Thermal Hydraulics(NURETH-7), 1995.
• 二ノ方壽. 高速炉における伝熱流動, 伝熱研究, Vol. 34, No. 133, pp. 60-69, 1995.
• T. Muramatsu, H. Ninokata. Adaptive Control System Using the Fuzzy Theory for Transient Multi-Dimensional Thermohydraulics Calculations jointly authored, International Journal for Numerical Methods in Engineering, No. 37, pp. 3397-3415, 1994.
• HISASHI NINOKATA. Investigation of Turbulence Modeling in Thermal Stratification Analysis jointly authored, Nuclear Engineering and Design, No. 150, pp. 81-93, 1994.
• H. Ninokata, T. Shimizu. Fast Reactor Safety and Computational Thermo-Fluid Dynamics Approaches, Proc. Joint Int. Cont. Mathematical Methods and Supercomputing in Nuclear Applications, pp. 151, 1993.
• HISASHI NINOKATA. An Overview of the BWR Subchannel Analysis Code Development and Experiments for Japanese Utilities, Electric Power Research Institute, 1993.
• HISASHI NINOKATA. In-Vessel Thermohydraulics Evaluation of a UTOP Accident and DN Precursor Concentration Transport Analysis Using a Multi-Dimensional Code, Nuclear Technology, No. 97, pp. 186, 1992.
• HISASHI NINOKATA. Key Issues in R&Ds and Their Prospective views Related to LMFBR Core Disruptive Accidents, Proc. Int. Conference on Design and Safety of Advanced Nuclear Power Plants(ANP'92), 1992.
• HISASHI NINOKATA. Thermohydraulics Analysis of local Subassembly Accidents in Liquid Metal Cooled Fast Breeder Reactors, Proc. 5th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics, 1992.
• HISASHI NINOKATA. Thermal Striping Temperature Fluctuation Analysis Using the Algebraic Stress Turbulence Model in Water and Sodium, JSME International Journal, Series II, Vol. 35, No. 4, pp. 486, 1992.
• H.NINOKATA. SABENA : Subassembly Boiling Evolution Numerical Analysis, Nuclear Engineering and Design, No. 120, pp. 349, 1990.
• HISASHI NINOKATA. Numerical Simulation of Oscillatory Convection in Low Pr Fluids, Notes on Numerical Fluid Mechanics, No. 27, pp. 90, 1990.
• HISASHI NINOKATA. Distributed Parameter Analysis for the Prediction of the Fine Structure of Flow and Temperature Fields in Wire Wrapped Pin Bundle Geometries, Nuclear Engineering and Design, No. 120, pp. 369, 1990.
• HISASHI NINOKATA. Assessment of the Physical Models in a Two-Fluid Model Code and Interpretation of Experiments, Nuclear Energy, Vol. 28, No. 3, pp. 161, 1989.
• HISASHI NINOKATA. Experimental Validation of the Subchannel Two-Fluid Model Code and Interpretation of Experiments, Proc. 4th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 1989.
• H.NINOKATA, etc.. Distributed resistance modeling of wire-wrapped rod bundles(共著), Nuclear Engineering and Design, Vol. 104, pp. 93-102, 1987.

著書

• 二ノ方壽. 軽水炉プラント 高速炉の変遷と現状 (分担), 日本原子力学会, Nov. 2010.
• 二ノ方壽. 乱流工学ハンドブック(分担) 21.9.1 軽水炉，高速炉, 朝倉書店, Nov. 2009.
• 二ノ方　寿. 機械工学便覧応用システム編　γ5エネルギー供給システム 4.7高速炉, 日本機械学会, pp. 134-139, May 2005.
• H. Ninokata, A. Wada, N. Tanaka. Fluid Modeling and Turbulence Measurements, World Scientific Publishing Co. Pte. Ltd., World Scientific Publishing Co. Pte. Ltd., 2002.
• H.NINOKATA. Fourth International Seminar on Subchannel Analysis, Institute of Applied Energy and Atomic Energy Society of Japan, Institute of Applied Energy and Atomic Energy Society of Japan, 1997.
• G.Basuque, M.Bottoni, D.Grand, F.Huber, H.Kottowski, M.Giot, H.NINOKATA, W.Peppler, B.Rameau, P.Riboud, K.Schleisiek, J.M.Seiler, N.Sheriff, R.Webster, J Macdou. LIQUID METAL THERMAL-HYDRAULICS, INFORUM Verlag und Verwaltungs GmbH, INFORUM Verlag und Verwaltungs GmbH, Dec. 1994.
• 二ノ方壽. 基礎高速炉工学, 日刊工業新聞社, 日刊工業新聞社, 1993.
• H.NINOKATA. Subchannel Analysis in Nuclear Reactors, Institute of Applied Energy and Atomic Energy Society of Japan, Institute of Applied Energy and Atomic Energy Society of Japan, 1992.

国際会議発表 (査読なし・不明)

• Hisashi Ninokata. Development of the Advanced Subchannel Analysis Code, Plenary Lecture, Fifth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-5), Korea Nuclear Society, pp. PL02, Nov. 2006.
• Tsunayuki Okumura, Elia Merzari, Hisashi Ninokata. Direct Numerical Simulation of Turbulent Flows in an Eccentric Annulus Channel, ANS Winter Meeting, American Nuclear Society, pp. on CDROM, Nov. 2006.
• Tsugio Yokoyama, Moriyasu Tokiwai, Hisashi Ninokata, Hiroshi Endo. Aluminum-Metal Fueled Long Life Fast Reactor Cores with Inherent Safety Features, ANS Winter Meeting, American Nuclear Society, pp. on CDROM, Nov. 2006.
• E. Merzari1, H. Ninokata, E. Baglietto. LES Simulation of the Vortex Street Between Rectangular Channels, Fifth Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-5), Korea Nuclear Society, pp. C101, Nov. 2006.
• B. Petrovic, M. Carelli, M. Ricotti, N. Todreas, F. Oriolo, N. Cavlina, H. Ninokata. Integrating Students Research into IRIS Design Development, ANS Annual Meeting, American Nuclear Society, on CDROM, June 2006.
• M.D. Carelli, B. Petrović, M. Ricotti, N. Todreas, N. Čavlina, F. Oriolo, H. Ninokata. Role of University Research in the Development of IRIS, International Youth Nuclear Congress (IYCN-2006), European Nuclear Society, pp. on CDROM, June 2006.
• T. Yokoyama, M. Tokiwai, H. Ninokata, H. Endo. Optimization of Aluminum-Metal Fueled Fast Reactor Cores for Inherent Safety, ANS Winter Meeting 2005, Proc. ANS Winter Meeting (on CDROM), Vol. 1, Nov. 2005.
• H. Ninokata. Overview of Activities on Design and Technology Development for Integral Type PWRs around the World, IAEA Workshop on Deployment and application potential of integral type PWRs for developing countries, IAEA, Vol. 1, pp. CDROM, Nov. 2005.
• E. Baglietto, H. Ninokata. Improved turbulence modeling for performance evaluation of novel fuel designs, Proc NURETH11(on CDROM), pp. NURETH11-331, Oct. 2005.
• S. Wang, H. Ninokata. 3d flow simulation in the single blade row of one stage turbomolecular pump by Direct Simulation Monte Carlo method, NURETH11, Proc NURETH11(on CDROM), pp. NURETH11-279, Oct. 2005.
• S. Wang, H., Ninokata. Numerical simulation of 3D flow in turbomolecular pump by Direct Simulation Monte Carlo method, 2005 ASME Fluids Engineering Division Summer Meeting and Exhibition, ASME Proceedings of FEDSM2005, Vol. 1, pp. FEDSM2005-77364, June 2005.
• K. Miller, C.V. Lombardi, M.E. Ricotti, A.C.O. Barroso, J.M. Collado, N.E. Todreas, H. Ninokata, et al. IRIS design overview and status update, 13th International Conference on Nuclear Engineering (ICONE-13), ASME ICONE13, pp. ICONE13-50442, May 2005.
• E. Baglietto, H. Ninokata. Improved anisotropic turbulence modeling for CFD applications in the IRIS design, 13th International Conference on Nuclear Engineering (ICONE-13), ASME ICONE13, pp. ICONE13-50143, May 2005.
• H. Ninokata. CFD Applications to Subchannel Turbulent Flows in a Rod Bundle, CFD Seminar on the Computational Fluid Dynamics Applications in Nuclear Industry 13th International Conference on Nuclear Engineering (ICONE-13), ASME ICONE13, Vol. 1, May 2005.
• E. Baglietto, H. Ninokata, T. Misawa. CFD and DNS methodologies development for fuel bundle simulations, ICONE13, ASME ICONE13, pp. ICONE13-50144, May 2005.
• M. Carelli, B. Petrovic, K. Miller, C. Lombardi, M. Ricotti, N. Cavlina, D. Grgic, J. Collado, L. Cinotti, A. Barroso, H. Ninokata, N. Crucitti, F. Henning, D. Ingersoll, N. Todreas, N. Kodochigov, G. Alonso, F. Orioro, J. Augutis, W. Griffith, C. Frederico, R. Boroughs, B. Panella, A. Naviglio. The IRIS Consortium: International cooperation in advanced reactor development, 13th International Conference on Nuclear Engineering (ICONE-13), ASME ICONE13, Vol. 1, pp. ICONE13-50799, May 2005.
• S. Wang, H. Ninokata. Analysis of pumping performances in one-stage turbomolecular pump by 3D direct simulation Monte Carlo calculation, 13th International Conference on Nuclear Engineering (ICONE-13), ASME ICONE13, Vol. 1, pp. ICONE13-50937, May 2005.

国内会議発表 (査読なし・不明)

• 二ノ方　寿, 奥村　剛征, 阿竹　規男. 高速炉燃料集合体内低Re数乱流の局所層流化について, 日本機械学会2006年度年次大会, 日本機械学会2006年度年次大会要旨集, pp. 2637、S-57, Sept. 2006.
• 内藤正則, 内田俊介, 越塚誠一, 二ノ方寿, 湊明彦, 斎藤裕明, 堀田浩司, 秋山実, 穴原直樹, 堂崎浩二. 連成解析による気液二相流中構造部物の振動・腐食評価手法の開発；1. 開発目的と概要, 日本原子力学会2006年秋の大会, 日本原子力学会2006年秋の大会要旨集, pp. L-17, Sept. 2006.
• 湊明彦, 越塚誠一, 二ノ方寿, 内藤正則, 内田俊介, 斎藤裕明, 秋山実. 連成解析による気液二相流中構造部物の振動・腐食評価手法の開発；４. オリフィスによる湿り蒸気噴流の数値解析, 日本原子力学会2006年秋の大会, 日本原子力学会2006年秋の大会要旨集, pp. L-20, Sept. 2006.
• 金子順一, 二ノ方　寿, 湊　明彦. 燃料集合体サブチャンネル体系内気液二相流の多次元解析, 日本原子力学会2006年春の年会, 日本原子力学会2006年春の年会要旨集, pp. L-38, Mar. 2006.
• 金子順一, 湊 明彦, 二ノ方 壽. 拡張二流体モデルを用いた燃料集合体サブチャンネル内二相流の多次元解析, 第18回計算力学講演会, Vol. 1, Nov. 2005.
• 19.山本雄一, 堀江英樹, 山本　泰, 白川典幸, 大川富雄, 二ノ方　壽, 越塚誠一. 広範囲の燃料格子に適用する汎用沸騰遷移解析手法に関する技術開発（5）液滴再付着効果とスペーサ効果, 日本原子力学会2005年秋の大会, 日本原子力学会, pp. G-16, Sept. 2005.
• 白井浩嗣, 堀田亮年, 工藤義朗, 山本　泰, 二ノ方　壽. 広範囲の燃料格子に適用する汎用沸騰遷移解析手法に関する技術開発（6）改良3流体場サブチャンネルコードの総合的検証, 日本原子力学会2005年秋の大会, 日本原子力学会, pp. G-17, Sept. 2005.
• 二ノ方　壽, 藤井敏浩, 山本　泰, 師岡慎一, 芹澤昭示, 三島嘉一郎, 佐田富道雄, 大川富雄, 越塚誠一, 冨山明男, 工藤義朗, 堀田亮年, 茶木雅夫. 広範囲の燃料格子に適用する汎用沸騰遷移解析手法に関する技術開発（1）技術開発成果のまとめ, 日本原子力学会2005年秋の大会, 日本原子力学会, pp. G-12, Sept. 2005.
• 18.堀田亮年, 白井浩嗣, 千年宏昌, 川原顕麿呂, 佐田富道雄, 二ノ方　壽. 広範囲の燃料格子に適用する汎用沸騰遷移解析手法に関する技術開発（3）クロスフローデータベース構築と構成方程式改良, 日本原子力学会2005年秋の大会, 日本原子力学会, pp. G-14, Sept. 2005.
• 二ノ方　寿. 原子炉工学におけるCFDの役割, 2005 JSME年次大会 基調講演【K16】, 2005 JSME年次大会講演資料集, pp. 500-501, Sept. 2005.
• 湊 明彦, 二ノ方 壽, 越塚 誠一, 三澤 雅樹. 原子炉における気液二相流複雑流動評価に関する技術開発(１)　（複雑な気液二相流の数値解析技術開発）, 日本混相流学会年会講演会2005, Vol. 1, July 2005.
• 千年宏昌, 堀田亮年, 二ノ方寿. 広範囲の燃料格子に適用する汎用沸騰遷移解析手法に関する技術開発：サブチャンネルにおける詳細速度場モデルの開発, 日本原子力学会　２００５年春の年会, 日本原子力学会　２００５年春の年会要旨集II　H-34, Vol. II, pp. H-34, Mar. 2005.
• 藤木尚, 横山次男, 二ノ方寿. 高速炉金属燃料炉心における自己制御性の炉心形状依存性の研究, 日本原子力学会　２００５年春の年会, 日本原子力学会　２００５年春の年会要旨集, Vol. II, pp. E-18, Mar. 2005.
• Y. Kumagai, H. Ninokata, D.J. Finnicum, A. Maioli. The preliminary PRA-based seismic margin assessment of the IRIS plant, 日本原子力学会　２００５年春の年会, 日本原子力学会　２００５年春の年会要旨集, Vol. Ⅱ, pp. H-37, Mar. 2005.
• 阿竹規男, 二ノ方寿, 三沢丈治, 大島宏之. 直接乱流シミュレーションによる稠密格子燃料集合体内の乱流特性評価, 日本原子力学会　２００５年春の年会, 日本原子力学会　２００５年春の年会要旨集, Vol. Ⅱ, pp. Ｈ-30, Mar. 2005.
• 中田耕太郎, 二ノ方寿. 原子力プラントにおける火災や燃焼化学反応を伴う熱流動問題研究専門委員会報告（5）過去の事例, 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. （5）, 2004.
• 二ノ方寿, 内藤俶孝, 石塚龍雄. 計算科学技術部会「計算結果評価法専門委員会活動報告」専門委員会活動概況, 日本原子力学会　２００４年春の年会要旨集, Vol. II, pp. (6), 2004.

その他の論文・著書など

• H. Ninokata. An overview of the microscopic approaches to thermal hydraulics computations of fluid transport phenomena in energy exchanges,, Int J Transport Phenomena, Vol. 7, pp. 219-240, July 2005.

学位論文

• 高速炉UTOP時の燃料集合体内冷却材挙動に関する研究,  本文,  Doctor of Engineering,  東京大学,  1977/--/--, 

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