過酷事故を起こさない受動的安全システムの開発
キーワード：過酷事故, 受動安全, 次世代原子炉
2020.04.

IVRに関わる熱流動現象の解明と機構論的モデルの開発
キーワード：IVR, 熱流動現象, 機構論的モデル
2020.04.

多成分多相流現象の数値シミュレーション技術の開発
キーワード：多相流, 数値シミュレーション, 数値流体力学
2020.04.

ソースタームを伴うエアロゾルの移行挙動に関する研究
キーワード：ソースターム, エアロゾル, 過酷事故
2020.04.

Global human resources training project to secure major design technologies for revitalizing SMR export
2024.10～2025.09, 代表者：Jae-Ho Jeong, Gachon University (Korea), Korea Institute of Energy Technology Evaluation and Planning (Korea).

高速炉実証炉開発事業（基盤研究と技術開発）プロジェクト
2023.12～2027.03, 日本原子力研究開発機構, 経済産業省資源エネルギー庁.

主要著書

1.	宗像健三、守田幸路, 輸送現象の基礎, コロナ社, 2006.10.

主要原著論文

1.	Xiaoxing Liu, Koji Morita, Shuai Zhang, An ALE pairwise-relaxing meshless method for compressible flows, Journal of Computational Physics, 10.1016/j.jcp.2019.02.037, 387, 1-13, 2019.06, [URL], In this paper, we present a pairwise-relaxing meshless (PRM) method for solving the Euler equations of compressible flows within the Arbitrary Lagrangian Eulerian (ALE) framework. Derived from the moving particle semi-implicit (MPS) method and the finite volume particle (FVP) method, the PRM approximates the derivatives from the value defined at the midpoint of each interacting particle pairs through a kernel-based formulation. Pairwise-relaxing constants are introduced to the kernels to provide degree of freedom to enforce the Taylor-series consistency condition while mass, momentum and energy are conserved exactly. An upwind high-order reconstruction scheme via a corrective procedure and variable cut-off radius is also developed for this PRM method. The HLLC approximate Riemann solver is adopted to solve Riemann problem. One and two-dimensional numerical tests are presented to demonstrate the performance of the PRM method..
2.	Koji Morita, Tatsuya Matsumoto, Shinpei Nishi, Tatsuya Nishikido, Songbai Cheng, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, A new empirical model for self-leveling behavior of cylindrical particle beds, journal of nuclear science and technology, 10.1080/00223131.2015.1126204, 53, 5, 713-725, 2016.05, [URL], During the material relocation phase of core disruptive accidents in sodium-cooled fast reactors, the rapid quenching and fragmentation of molten materials discharged from the reactor core into the lower plenum region can lead to the formation of debris beds. Coolant boiling may lead to leveling of the mound-shaped beds, which changes both the beds' coolability with decay heat in the fuel and the neutronic characteristics. In this study, a series of experiments using simulant materials were performed to develop an experimental database of self-leveling processes of particle beds in a cylindrical system. To simulate the coolant boiling in the beds in the experiments, a gas injection method was used to percolate nitrogen gas uniformly through the base of a bed with a conical-shaped mound. Time variations in bed height during the self-leveling process were measured for different particle sizes, densities and sphericities, and gas injection velocities. Using a dimensional analysis approach, a new model was proposed. This model correlates the experimental data on transient bed height with an empirical equation using a characteristic time for self-leveling development and an equilibrium bed height. The proposed model reasonably predicts the self-leveling development of particle beds..
3.	K. MORITA, S. ZHANG, S. KOSHIZUKA, Y. TOBITA, H. YAMANO, N. SHIRAKAWA, F. INOUE, H. YUGO, M. NAITOH, H. OKADA, Y. YAMAMOTO, M. HIMI, E. HIRANO, S. SHIMIZU, M. OUE, Detailed Analyses of Key Phenomena in Core Disruptive Accidents of Sodium-cooled Fast Reactors by the COMPASS Code, Nuclear Engineering and Design, 241, 12, 4672-4681, 2011.12.
4.	B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Self-Leveling Onset Criteria in Debris Beds, J. Nuclear Science and Technology, 47, 4, 384-395, 2010.04.
5.	M. Kabir HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-pin Bundle Experiment, J. Nuclear Science and Technology, Vol.46, No.8, pp.799-808, 2009.08.
6.	S. ZHANG, S. KUWABARA, T. SUZUKI, Y. KAWANO, K. MORITA, K. FUKUDA, Simulation of Solid–fluid Mixture Flow Using Moving Particle Methods, J. Computational Physics, Vol.228, Issue 7, pp.2552-2565, 2009.04.
7.	M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK, Simulation of Molten Metal Freezing Behavior onto a Structure, Nuclear Engineering and Design, Vol.238, Issue 10, pp.2706-2717, 2008.10.
8.	Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Hidemasa YAMANO, Ikken SATO, Experimental Verification of the Fast Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behavior with Condensation, Nuclear Engineering and Design, Vol.238, Issue 1, pp.49-56, 2008.01.
9.	Ping LIU, Satoshi YASUNAKA, Tatsuya MATSUMOTO, Koji MORITA, Kenji FUKUDA, Hidemasa YAMANO, Yoshiharu TOBITA, Dynamic Behavior of a Solid Particle Bed in a Liquid Pool, SIMMER-III Code Verification, Nuclear Engineering and Design, Vol.237, No.5, pp.524-535, 2007.03.
10.	Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano, Thermophysical Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis, J. Nuclear Science and Technology, Vol.43, No. 5, pp.1-11, 2006.05.
11.	Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa, An Improved MPS Method for Numerical Simulations of Convective Heat Transfer Problems, Int. J. Numerical Methods in Fluids, Vol.51, No. 1, pp. 31-47, 2006.05.
12.	Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita, Simulation of the Dynamic Behavior of the Solid Particle Bed in a Liquid Pool: Sensitivity of the Particle Jamming and Particle Viscosity Models, J. Nuclear Science and Technology, Vol.43, No. 2, pp.140-149, 2006.02.
13.	K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification, Nuclear Engineering and Design, 10.1016/S0029-5493(02)00351-5, 220, 3, 224-239, Vol. 220, No. 3, pp. 224-239, 2003.01.
14.	K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear, SIMMER-III Applications to Fuel-Coolant Interactions, Nuclear Engineering and Design, Vol. 189, pp. 337-357, 1999.01.
15.	K. Morita, E. A. Fischer, K. Thurnay, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part II: Properties of Fast Reactor Materials, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 193-211, 1998.01.
16.	K. Morita, E. A. Fischer, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part I: Analytic Equation-of-State Model, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 177-191, 1998.01.

主要総説, 論評, 解説, 書評, 報告書等

1.	H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, Sa. Kondo, K. Morita, M. Sugaya, M. Mizuno, S. Hosono, T. Kondo, SIMMER-IV: Three Dimensional Computer Program for LMFR Core Disruptive Accident Analysis -Version 2.A Model Summary and Program Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-070, 2003.08.
2.	H. Yamano, S. Fujita, Y. Tobita, K. Kamiyama, Sa. Kondo, K. Morita, E. A. Fischer, D. J. Brear, N. Shirakawa, X. Cao, M. Sugaya, M. Mizuno, S. Hosono, T. Kondo, W. Maschek, E. Kiefhaber, G. Buckel, A. Rineiski, M. Flad, T. Suzuki, P. Coste, S. Pigny, J. L, SIMMER-III: A Computer Program for LMFR Core Disruptive Accident Analysis -Version 3.A Model Summary and Program Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-071, 2003.08.
3.	K. Morita, H. Yamano, Y. Tobita, Sa. Kondo, SIMMER-III/IV Heat- and Mass-Transfer Model - Model and Method Description -, Japan Nuclear Cycle Development Institute, JNC TN9400 2003-047, 2003.07.
4.	二ノ方 壽　他16名, 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. 14-31, 2000.12.
5.	K. Morita, Y. Tobita, Sa. Kondo, E. A. Fischer, SIMMER-III Analytic Thermophysical Property Model, Japan Nuclear Cycle Development Institute, JNC TN9400 2000-004, 1999.05.
6.	K. Morita, Y. Tobita, Sa. Kondo, E. A. Fischer, K. Thurnay, SIMMER-III Analytic Equation-of-State Model, Japan Nuclear Cycle Development Institute, JNC TN9400 2000-005, 1999.05.

主要学会発表等

1.	守田幸路, 山野秀将, 飛田吉春, 炉心物質再配置過程解析コード SIMMER-LTの熱・物質移行モデルの開発, 日本原子力学会「2010秋の大会」, 2010.09.
2.	守田幸路，田上慎一，松元達也，福田研二，飛田吉春，山野秀将，佐藤一憲, 非凝縮性ガスを伴う大スケール蒸気泡の過渡凝縮挙動, 日本原子力学会「2005年秋の大会」, 2005.09.
3.	守田幸路, 飛田吉春, 山野秀将, Werner Maschek, Michael Flad, 原子炉安全解析で用いる鉛−ビスマス合金の状態方程式, 日本原子力学会「2004年秋の大会」, 2004.09.
4.	守田幸路，飛田吉春，曹　学武，Pierre Coste，Werner Maschek, 高速炉の核熱流力安全解析コードSIMMER-IIIの検証研究(4)燃料−冷却材相互作用, 日本原子力学会「2003年秋の大会」, 2003.09.
5.	守田幸路，藤本登，福田研二，飛田 吉春，山野 秀将，近藤 悟, 炉心損傷時の多成分蒸発／凝縮現象のモデル化手法に関する研究, 日本原子力学会「2000年春の年会」, 2000.03.

1.	越塚誠一, 守田幸路, 財団法人エネルギー総合工学研究所, 日本システム株式会社, COMPASS（ソフトウェア情報センター, 登録番号　Ｐ第９９１３号—１）, 2010.10 ３次元熱流動・構造連成解析コード.

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