Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-pin Bundle Experiment Reviewed International journal

M. Kabir HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK

J. Nuclear Science and Technology   2009.8

Simulation of Solid–fluid Mixture Flow Using Moving Particle Methods Reviewed International journal

S. ZHANG, S. KUWABARA, T. SUZUKI, Y. KAWANO, K. MORITA, K. FUKUDA

J. Computational Physics   2009.4

Simulation of Molten Metal Freezing Behavior onto a Structure Reviewed International journal

M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK

Nuclear Engineering and Design   2008.10

Experimental Verification of the Fast Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behavior with Condensation Reviewed International journal

Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Hidemasa YAMANO, Ikken SATO

Nuclear Engineering and Design   2008.1

Dynamic Behavior of a Solid Particle Bed in a Liquid Pool, SIMMER-III Code Verification Reviewed International journal

Ping LIU, Satoshi YASUNAKA, Tatsuya MATSUMOTO, Koji MORITA, Kenji FUKUDA, Hidemasa YAMANO, Yoshiharu TOBITA

Nuclear Engineering and Design   2007.3

Thermophysical Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis Reviewed International journal

Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano

J. Nuclear Science and Technology   2006.5

An Improved MPS Method for Numerical Simulations of Convective Heat Transfer Problems Reviewed International journal

Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa

Int. J. Numerical Methods in Fluids   2006.5

Simulation of the Dynamic Behavior of the Solid Particle Bed in a Liquid Pool: Sensitivity of the Particle Jamming and Particle Viscosity Models Reviewed International journal

Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita

J. Nuclear Science and Technology   2006.2

Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification Reviewed International journal

K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo

Nuclear Engineering and Design   220 ( 3 )   224 - 239   2003.1

SIMMER-III Applications to Fuel-Coolant Interactions Reviewed International journal

K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear

Nuclear Engineering and Design   1999.1

Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part II: Properties of Fast Reactor Materials Reviewed International journal

K. Morita, E. A. Fischer, K. Thurnay

Nuclear Engineering and Design   1998.1

Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part I: Analytic Equation-of-State Model Reviewed International journal

K. Morita, E. A. Fischer

Nuclear Engineering and Design   1998.1

Investigations on aerosol transport and deposition behavior during severe reactor accident Reviewed International journal

#M.I. HOSAN, #K. TAKANISHI, @K. MORITA, @W. LIU, @X. CHENG

Mechanical Engineering Journal   11 ( 2 )   2024.3

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 －デバイス集合体の仕様選択拡張性とプラントにおける核不拡散性の検討－ Reviewed

@川島 正俊, @相楽 洋, @守田 幸路

第44回日本核物質管理学会年次大会論文集   #4412   2023.11

Preliminary Analysis of Severe Accident in Sodium-Cooled Fast Reactor Using Eutectic Reaction Model of Boron-Carbide Control-Rod Material Reviewed International journal

@H. YAMANO, @K. MORITA

Proc. of 20th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)   2023.8

Development of a Simplified One-Dimensional CDA Bubble Model for Source Term Evaluation Reviewed International journal

#Z. ZOU, @K. MORITA, @W. LIU

Proc. of 30th International Conference on Nuclear Engineering (ICONE30)   2023.5

A Large-Scale Particle-Based Simulation of Heat And Mass Transfer Behavior in EAGLE ID1 In-Pile Test Reviewed International journal

#T. ZHANG, #Y. YAO, @K. MORITA, @X. LIU, @W. LIU, @Y. IMAIZUMI, @K. KAMIYAMA

Proc. of 30th International Conference on Nuclear Engineering (ICONE30)   2023.5

Experimental Study on Accident Source Terms Transport and Deposition Behavior in Nuclear Power Plants Reviewed International journal

#M.I. HOSAN, #M. KOGA, #A. KAKOI, @K. MORITA, @W. LIU, @X. CHENG

Proc. of 30th International Conference on Nuclear Engineering (ICONE30)   2023.5

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (2) A study on Selecting Candidate Fuel Materials for the Basic Device Specifications Reviewed International journal

@H. SAGARA, @M. KAWASHIMA, @K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @I. SATO, @Y. SEKIO

Proc. of 30th International Conference on Nuclear Engineering (ICONE30)   2023.5

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (1) Safety Analysis of Device-loaded Cores with Different Fuel Materials Reviewed International journal

@K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @I. SATO, @Y. SEKIO, @H. SAGARA, @M. KAWASHIMA

Proc. of 30th International Conference on Nuclear Engineering (ICONE30)   2023.5

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study Reviewed International journal

@K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @I. SATO, @Y. SEKIO, @H. SAGARA, @M. KAWASHIMA

Journal of Nuclear Engineering and Radiation Science   9 ( 2 )   021301   2023.3

Eulerian vs Lagrangian Method for Low Computational Resources: A Comparison of 2D Dam Break Case Reviewed International journal

@R.S. MAHMUDAH, @K. MORITA

Trend in Science   20 ( 6 )   5539   2023.3

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications Reviewed International journal

@K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @I. SATO, @Y. SEKIO, @H. SAGARA, @M. KAWASHIMA

Journal of Nuclear Engineering and Radiation Science   9 ( 4 )   041302   2023.3

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発ーデバイス集合体の候補仕様選択とプラントにおける核不拡散性の検討ー Reviewed

@川島 正俊, @相楽 洋, @守田 幸路

第43回日本核物質管理学会年次大会論文集   #4304   2022.11

Particle-Based Simulation of Jet Impingement Behaviors Reviewed International journal

#D. TAKATSUKA, @K. MORITA, @W. LIU, #T. ZHANG, @T. NAKAMURA, @K. KAMIYAMA

Proc. of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12)   N12P1046   2022.10

Experimental Study on Aerosol Migration Behavior in Rectangular Penetrations Reviewed International journal

#M. KOGA, #K. TAKANISHI, @T. MATSUMOTO, @W. LIU, @K. MORITA, @K. NAKAMUR, @T. KANAI

Proc. of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12)   N12P1042   2022.10

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device Reviewed International journal

@K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @I. SATO, @Y. SEKIO, @H. SAGARA, @M. KAWASHIMA

Proc. of 2022 29th International Conference on Nuclear Engineering (ICONE29)   2022.8

A 3D Particle-Based Simulation of Heat and Mass Transfer Behavior in the EAGLE ID1 In-Pile Test Reviewed International journal

#T. ZHANG, @K. MORITA, @X. LIU, @W. LIU, @K. KAMIYAMA

Annals of Nuclear Energy   179   2022.8

Numerical Investigation on Mechanism of Heat Transfer between Molten Pool and Duct Wall in EAGLE ID1 and ID2 In-Pile Tests Reviewed International journal

#T. ZHANG, @K. MORITA, @W. LIU, @X. LIU, @K. KAMIYAMA

Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)   2022.3

Preliminary Application of Eutectic Reaction Model on Boron Carbide and Stainless Steel to Severe Accident Simulation of Sodium-Cooled Fast Reactors Reviewed International journal

@H. YAMANO, @K. MORITA

Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)   2022.3

Flow Characteristics in Rectangular Micro-Channels with High Aspect Ratios Reviewed International journal

@W. LIU, #K. GOTOU, @T. MATSUMOTO, @K. MORITA

Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)   2022.3

Mechanistic Critical Heat Flux Prediction for In-Vessel Retention Conditions Reviewed International journal

#M.A. RAFIQ AKAND, @W. LIU, @T. MATSUMOTO, @K. MORITA

Nuclear Engineering and Design   58 ( 384 )   2021.12

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 ―新たなデバイス概念の展開とデバイスの核不拡散性の検討－ Reviewed

@川島正俊, @相楽　洋, @守田幸路

第42回日本核物質管理学会年次大会論文集   2021.11

Comparisons between Passive RCCSs on Degree of Passive Safety Features against Accidental Conditions and Methodology to Determine Structural Thickness of Scaled-Down Heat Removal Test Facilities Reviewed International journal

@K. TAKAMATSU, @T. MATSUMOTO, @W. LIU, @K. MORITA

Annals of Nuclear Energy   162   2021.11

Experimental Study and Modeling of Bubble Lift-Off Diameter in Subcooled Flow Boiling Including the Inclination Effect of the Heating Surface Reviewed International journal

#M.A. RAFIQ AKAND, #K. KITAHARA, @T. MATSUMOTO, @W. LIU, @K. MORITA

Journal of Nuclear Science and Technology   58 ( 11 )   1195 - 1209   2021.11

Development of a Passive Reactor Shutdown Device for Prevention of Core Disruptive Accidents in Fast Reactors: Project Overview and Preliminary Results Reviewed International journal

@K. MORITA, @W. LIU, @T. ARIMA, @Y. ARITA, @K. KAWASE, @I. SATO, @H. MATSUURA, @Y. SEKIO, @M. KAWASHIMA

Proc. of the 28th International Conference on Nuclear Engineering (ICONE28)   2021.8

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019 Reviewed International journal

@HIDEMASA YAMANO, @TOSHIHIDE TAKAI, @TOMOHIRO FURUKAWA, @SHIN KIKUCHI, @YUKI EMURA, @KENJI KAMIYAMA, @HIROYUKI FUKUYAMA, @HIDEO HIGASHI, @TSUYOSHI NISHI, @HIROMICHI OHTA, @KOJI MORITA, @KINYA NAKAMURA

Proc. of the 28th International Conference on Nuclear Engineering (ICONE28)   2021.8

A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling Reviewed International journal

#MD. ADUR RAFIQ AKAND, @KOJI MORITA, @WEI LIU, @TATSUYA MATSUMOTO

Proc. of the 28th International Conference on Nuclear Engineering (ICONE28)   2021.8

A 3D Numerical Simulation On Heat Transfer Behavior in EAGLE ID1 In-Pile Test Using Finite Volume Particle Method Reviewed International journal

#TING ZHANG, @KOJI MORITA, @XIAOXING LIU, @WEI LIU, @KENJI KAMIYAMA

Proc. of the 28th International Conference on Nuclear Engineering (ICONE28)   2021.8

Comparison between Passive Reactor Cavity Cooling Systems Based on Atmospheric Radiation and Atmospheric Natural Circulation Reviewed International journal

@K. TAKAMATSU, @T. MATSUMOTO, @W. LIU, @K. MORITA

Annals of Nuclear Energy   151   2021.2

Machine‐learning‐based surface tension model for multiphase flow simulation using particle method Reviewed International journal

@X. LIU, @K. MORITA, @S. ZHANG

International Journal for Numerical Methods in Fluids   93 ( 2 )   356 - 368   2021.2

Numerical Simulation of Heat Transfer Behavior in EAGLE ID1 In-Pile Test Using Finite Volume Particle Method Reviewed International journal

#T. ZHANG, @K. FUNAKOSHI, @X. LIU, @W. LIU, @K. MORITA, @K. KAMIYAMA

Annals of Nuclear Energy   150   2021.1

Direct Numerical Simulation of Incompressible Multiphase Flow with Vaporization Using Moving Particle Semi-implicit Method Reviewed International journal

@X. LIU, @K. MORITA, @S. ZHANG

Journal Computational Physics   425   2021.1

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 ―新たなデバイス概念の基本評価と核不拡散性の検討― Reviewed

@川島正俊, @相楽　洋, @守田幸路

第41回日本核物質管理学会年次大会論文集   2020.11

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition Reviewed International journal

#M.A. RAFIQ AKAND, @T. MATSUMOTO, @W. LIU, @K. MORITA

International Topical Meeting on Advances in Thermal Hydraulics (ATH '20)   1074 - 1087   2020.10

Numerical Simulation of the Solid Particle Sedimentation and Bed Formation Behaviors Using a Hybrid Method Reviewed International journal

#MD A.R. SHEIKH, @X. LIU, @T. MATSUMOTO, @K. MORITA, @L. GUO, @T. SUZUKI, @K. KAMIYAMA

Energies   13 ( 19 )   2020.9

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2018 Reviewed International journal

@H. YAMANO, @T. TAKAI, @T. FURUKAWA, @S. KIKUCHI, @Y. EMURA, @K. KAMIYAMA, @H. FUKUYAMA, @H. HIGASHI, @T. NISHI, @H. OHTA, @X. LIU, @K. MORITA

Proc. of ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE   2020.8

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (4) Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide Reviewed International journal

@X. LIU, @K. MORITA, @H. YAMANO

Proc. of ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE   2020.8

Comparative study of Two Corrective Gradient Models in the Simulation of Multiphase Flows Using Moving Particle Semi-Implicit Method Reviewed International journal

@X. LIU, @K. MORITA, @S. ZHANG

International Journal for Numerical Methods in Fluids   92 ( 6 )   573 - 586   2020.6

A stable moving particle semi-implicit method with renormalized Laplacian model improved for incompressible free-surface flows Reviewed

Xiaoxing Liu, Koji Morita, Shuai Zhang

Computer Methods in Applied Mechanics and Engineering   356   199 - 219   2019.11

Comparative methodology between actual RCCS and downscaled heat-removal test facility Reviewed

Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita

Annals of Nuclear Energy   133   830 - 836   2019.11

A conservative finite volume-particle hybrid method for simulation of incompressible interfacial flow Reviewed

Xiaoxing Liu, Koji Morita, Shuai Zhang

Computer Methods in Applied Mechanics and Engineering   355   840 - 859   2019.10

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (5) Validation of a Multi-Phase Model for Eutectic Reaction Between Molten Stainless Steel and B₄C Reviewed International journal

@X.LIU, @K. MORITA, @H. YAMANO

Proc. of International Nuclear Fuel Cycle Conference (Global 2019)   47 - 51   2019.9

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project overview Reviewed International journal

@H. YAMANO, @T. TAKAI, @T. FURUKAWA, @S. KIKUCHI, @Y. EMURA, @K. KAMIYAMA, @H. FUKUYAMA, @H. HIGASHI, @T. NISHI, @H. OTA, @HIROMICHI, @X.LIU, @K. MORITA, @K. NAKAMURA, @H. OTA, @M. FURUYA

Proc. of International Nuclear Fuel Cycle Conference (Global 2019)   418 - 427   2019.9

A pairwise-relaxing incompressible smoothed particle hydrodynamics scheme Reviewed

Xiaoxing Liu, Koji Morita, Shuai Zhang

Computer Methods in Applied Mechanics and Engineering   348   297 - 312   2019.5

Self-leveling behavior of mixed solid particles in cylindrical bed using gas-injection method Reviewed

Le Hoang Sang Phan, Phi Manh Ngo, Ryo Miura, Yusuke Tasaki, Tatsuya Matsumoto, Wei Liu, Koji Morita

Journal of nuclear science and technology   56 ( 1 )   111 - 122   2019.1

Improvement of heat-removal capability using heat conduction on a novel reactor cavity cooling system (RCCS) design with passive safety features through radiation and natural convection Reviewed

Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita

Annals of Nuclear Energy   122   201 - 206   2018.12

Validation of Three-Dimensional Finite-Volume-Particle Method for Simulation of Liquid-Liquid Mixing Flow Behavior Reviewed International journal

#M. KATO, #K. FUNAKOSHI, @X. LIU, @T. MATSUMOTO, @W. LIU, @K. MORITA, @K. KAMIYAMA

Proc. of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11)   N11P0033   2018.11

Experimental Study on Heat Removal Performance of A New Reactor Cavity Cooling System (RCCS) Reviewed International journal

#S. HOSOMI, #T. AKASHI, @T. MATSUMOTO, @W. LIU, @K. MORITA, @K. TAKAMATSU

Proc. of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11)   N11P0045   2018.11

Particle-based Simulation of Heat Transfer Behavior in EAGLE ID1 In-Pile Test Reviewed International journal

@K. MORITA, #R. OGAWA, #H. TOKIOKA, @X. LIU, @W. LIU, @K. KAMIYAMA

Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12)   Paper No. 683   2018.10

Numerical Simulation on Self-leveling Behavior of Mixed Particle Beds Using Multi-fluid Model Coupled with DEM Reviewed International journal

#L.H.S. PHAN, #Y. OHARA, #R. KAWATA, @X. LIU, @W. LIU, @K. MORITA, @L. GUO, @K. KAMIYAMA, @H. TAGAMI

Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12)   Paper No. 737   2018.10

Modeling of Eutectic Reaction Between Molten Stainless Steel and B4C for Severe Accident Simulations Reviewed International journal

@X. LIU, @K. MORITA, @H. YAMANO

Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12)   Paper No. 572   2018.10

Accuracy and stability enhancements in the incompressible finite-volume-particle method for multiphase flow simulations Reviewed

Xiaoxing Liu, Ryusei Ogawa, Masatsugu Kato, Koji Morita, Shuai Zhang

Computer Physics Communications   230   59 - 69   2018.9

An advanced moving particle semi-implicit method for accurate and stable simulation of incompressible flows Reviewed

Xiaoxing Liu, Koji Morita, Shuai Zhang

Computer Methods in Applied Mechanics and Engineering   339   467 - 487   2018.9

Sedimentation behavior of mixed solid particles Reviewed

Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Kenichi Matsuba, Kenji Kamiyama, Tohru Suzuki

journal of nuclear science and technology   55 ( 6 )   623 - 633   2018.6

Model for particle behavior in debris bed Reviewed

Hirotaka Tagami, Songbai Cheng, Yoshiharu Tobita, Koji Morita

Nuclear Engineering and Design   328   95 - 106   2018.3

Experimental study on debris bed characteristics for the sedimentation behavior of solid particles used as simulant debris Reviewed

M. Shamsuzzaman, T. Horie, F. Fuke, M. Kamiyama, T. Morioka, Tatsuya Matsumoto, Koji Morita, H. Tagami, T. Suzuki, Y. Tobita

Annals of Nuclear Energy   111   474 - 486   2018.1

Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors Reviewed

Werner Maschek, Rui Li, Claudia Matzerath Boccaccini, Fabrizio Gabrielli, Koji Morita

Nuclear Engineering and Design   326   392 - 402   2018.1

Enhancement of the accuracy of the finite volume particle method for the simulation of incompressible flows Reviewed

X. Liu, K. Morita, S. Zhang

International Journal for Numerical Methods in Fluids   85 ( 12 )   712 - 726   2017.12

Experimental Study on Self-Leveling Behavior of Binary-Mixed Particles in Cylindrical Bed Using Gas-Injection Method Reviewed International journal

#L.H.S. PHAN, #P.M. NGO, #F. MATSUOKA, #R. MIURA, @T. MATSUMOTO, @K. MORITA

Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)   2017.9

IAEA's Coordinated Research Project on EBR-II Shutdown Heat Removal Tests Reviewed International journal

@C. BATRA, @V. KRIVENTSEV, @S. MONTI, @L. BRIGGS, @G. SU, @W. HU, @D. SUI, @L. MAAS, @B. VEZZONI, @U. P. SARATHY, @A. DEL NEVO, @A. PETRUZZI, @R. ZANINO, @H. OHIRA, @W. F. G. VAN ROOIJEN, @K. MORITA, @C. CHOI, @A. SHIN, @M. STEMPNIEWICZ, @N. RTISCHEV, @K. MIKITYUK, @E. BATES

Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)   2017.9

Numerical Simulation of Solid-Particle Sedimentation Behavior Using a Multi-Fluid Model Coupled with DEM Reviewed International journal

#R. KAWATA, #Y. OHARA, #M.A.R. SHEIKH, @X. LIU, @T. MATSUMOTO, @K. MORITA, @L. GUO, @K. KAMIYAMA, @T. SUZUKI

Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17)   2017.9

EBR-II Passive Safety Demonstration Tests Benchmark Analyses Reviewed International journal

@L. BRIGGS, @V. KRIVENTSEV, @A. PETRUZZI, @R. ZANINO, @H. OHIRA, @W. VAN ROOIJEN, @K. MORITA, @C. CHOI, @A. SHIN, @M. STEMPNIEWICZ, @N. RTISCHEV, @K. MIKITYUK, @S. MONTI, @E. BATES, @W. HU, @D. SUI, @G. SU, @L. MAAS, @B. VEZZONI, @U. SARATHY, @A. DEL NEVO

Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development   2017.6

IAEA's Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview Reviewed International journal

@V. KRIVENTSEV, @C. BATRA, @D. ALESSANDRO, @P. ALESSANDRO, @R. ZANINO, @H. OHIRA, @W. VAN ROOIJEN, @K. MORITA, @C. CHOI, @A. SHIN, @M. STEMPNIEWICZ, @N. RTISHCHEV, @S. MONTI, @K. MIKITYUK, @E. BATES, @L. BRIGGS, @W. HU, @D. SUI, @G. SU, @L. MAAS, @B. VEZZONI, @P. UPPALA

Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development   2017.6

Final Results and Lessons Learned From EBR-II SHRT-17 Benchmark Simulations Reviewed International journal

@N. RTISHCHEV, @H. OHIRA, @L. BRIGGS, @S. MONTI, @V. KRIVENTSEV, @W. HU, @D. SUI, @G. SU, @L. MAAS, @B. VEZZONI, @U. SARATHY, @A. DEL NEVO, @R. ZANINO, @A. PETRUZZI, @W. VAN ROOIJEN, @K. MORITA, @C. CHOI, @A. SHIN, @M. STEMPNIEWICZ, @Y. ZHANG, @E. BATES

Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development   2017.6

SIMMER Analyses of the EBR-II Shutdown Heat Removal Tests Reviewed International journal

@B. VEZZONI, @M. MARCHETTI, @L. ANDRIOLO,@F. GABRIELLI, @X. CHEN, @C. MATZERATH BOCCACCINI, @A. RINEISKI, @W. MASCHEK, @K. MORITA, @T. ARIMA

Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development   2017.6

The Status of Safety Research in the Field of Sodium-Cooled Fast Reactors in Japan Reviewed International journal

@S. KUBO, @K. MORITA, @K. KAMIYAMA, @T. SUZUKI

Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development   2017.6

Numerical simulations on self-leveling behaviors with cylindrical debris bed Reviewed

Liancheng Guo, Koji Morita, Yoshiharu Tobita

Nuclear Engineering and Design   315   61 - 68   2017.4

Particle-based simulation of Rayleigh-Taylor instability Reviewed

Nur Asiah Aprianti, Sparisoma Viridi, Zaki Su'ud, Koji Morita

5th International Conference on Advances in Nuclear Science and Engineering, ICANSE 2015 Journal of Physics: Conference Series   799 ( 1 )   2017.2

Particle-based simulation of Rayleigh-Taylor instability Reviewed

@N.A. APRIANTI, @S. VIRIDI, @Z. SU'UD, @K. MORITA

Journal of Physics: Conference Series   799   2017.2

Experimental Database for Bed Formation Behaviors of Solid Particles Reviewed International journal

Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Ken-ichi Matsuba, Kenji Kamiyama, Tohru Suzuki

Proc. of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10)   2016.11

Numerical Simulation of Jet Breakup in Coolant Using A Mesh-Particle Hybrid Method Reviewed International journal

LIU XIAOXING, Koji Morita, Shuai Zhang

Proc. of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10)   2016.11

Experimental Investigation on Characteristics of Mixed Particle Debris in Sedimentation and Bed Formation Behavior Reviewed International journal

Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Ken-ichi Matsuba, Kenji Kamiyama, Tohru Suzuki

Proc. of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11)   2016.10

New reactor cavity cooling system (RCCS) with passive safety features A comparative methodology between a real RCCS and a scaled-down heat-removal test facility Reviewed

Kuniyoshi Takamatsu, Tatsuya Matsumoto, Koji Morita

Annals of Nuclear Energy   96   137 - 147   2016.10

Numerical Simulation of Droplet Breakup Using a Mesh-Particle Hybrid Method Reviewed International journal

LIU XIAOXING, Koji Morita, Shuai Zhang

Proc. of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11)   2016.10

Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations Reviewed International journal

LIU XIAOXING, GUO LIANCHENG, Koji Morita, S. ZHANG

International Journal for Numerical Methods in Fluids   82 ( 6 )   334 - 347   2016.8

SIMMER/PARTISN Analyses of EBR-II Shutdown Heat Removal Tests Reviewed International journal

B. VEZZONI, M. MARCHETTI, L. ANDRIOLO, F. GABRIELLI, X.-N. CHEN, C. MATZERATH BOCCACCINI, A. RINEISKI, W. MASCHEK, Koji Morita, Tatsumi Arima

Proc. of Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century   6   3973 - 3982   2016.5

Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors Reviewed

Yoshiharu Tobita, Kenji Kamiyama, Hirotaka Tagami, Ken Ichi Matsuba, Tohru Suzuki, Mikio Isozaki, Hidemasa Yamano, Koji Morita, Liancheng Guo, Bin Zhang

journal of nuclear science and technology   53 ( 5 )   698 - 706   2016.5

New Reactor Cavity Cooling System with A Novel Shape and Passive Safety Features Reviewed International journal

K. TAKAMATSU, Tatsuya Matsumoto, Koji Morita

Proc. of International Congress on Advances in Nuclear Power Plants, ICAPP 2016   2   1250 - 1257   2016.4

Numerical Simulations of Gas–Liquid–Particle Three-Phase Flows Using a Hybrid Method Reviewed International journal

Liancheng Guo, Koji Morita, Yoshiharu Tobita

Journal of Nuclear Science and Technology   53 ( 2 )   271 - 280   2016.2

Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations Reviewed International journal

Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang

International Journal for Numerical Methods in Fluids   2016.2

Numerical Simulation of Gas-Liquid-Solid Three-Phase Flow Using Particle Methods Reviewed International journal

Xaoxing Liu, Yuki Aramaki, Liancheng Guo, Koji Morita

Journal of Nuclear Science and Technology   52 ( 12 )   1480 - 1489   2015.12

EBR-II Passive Safety Demonstration Tests Benchmark Analyses-Phase 2 Reviewed International journal

L. BRIGGS, W. HU, G. H. SU, B. VEZZONI, A. DEL NEVO, S. MONTI, D. SUI, L. MAAS, U. P. SARATHY, A. PETRUZZI, R. ZANINO, H. OHIRA, H. MOCHIZUKI, Koji Morita, C. CHOI, A. SHIN, M. STEMPNIEWICZ, N. RTISHCHEV, Y. ZHANG

Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015   4   3030 - 3043   2015.9

A Study on Characteristics of Molten Pool Sloshing in Core Disruptive Accidents of Fast Reactors Reviewed International journal

Isao Tatewaki, Koji Morita, Hiroshi Endo

Proc. of 23rd International Conference on Nuclear Engineering (ICONE23)   2015.5

Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations with Phase Change Reviewed International journal

Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang

Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10)   2014.12

Validation of New Empirical Model for Self-Leveling Behavior of Cylindrical Particle Beds Based on Experimental Database Reviewed International journal

Koji Morita, Tatsuya Matsumoto, Syohei Taketa, Sinpei Nishi, Songbai Cheng, Tohru Suzuki, Yoshiharu Tobita

Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10)   2014.12

Development of the Evaluation Methodology for the Material Relocation Behavior in the Core Disruptive Accident of Sodium-Cooled Fast Reactors Reviewed International journal

Yoshiharu Tobita, Kenji Kamiyama, Hirotaka Tagami, Ken-ichi Matsuba, Tohru Suzuki, Mikio Isozaki, Hidemasa Yamano, Koji Morita, Liancheng Guo, Bin Zhang

Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10)   2014.12

A Hybrid Particle-Mesh Method for Simulation of Mixed Incompressible and Compressible Flows Reviewed International journal

Xiaoxing Liu, Koji Morita

Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9)   2014.11

Investigation on Sloshing Response of Liquid in a 2D Pool against Hydraulic Disturbance Reviewed International journal

Koji Morita, Tatsuya Matsumoto, Yuki Emura, Tatsuhiro Abe, Isao Tatewaki, Hiroshi Endo

Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9)   2014.11

Experimental Study on Sedimentation Behavior of Core Debris Reviewed International journal

Md. Shamsuzzaman, Tatsuya Matsumoto, Motoki Kamiyama, Tohru Morioka, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita

Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9)   2014.11

An Investigation on Debris Bed Self-Leveling Behavior with Non-Spherical Particles Reviewed International journal

Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Syohei Taketa, Sinpei Nishi, Tatsuya Nishikido, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Journal of Nuclear Science and Technology   51 ( 9 )   1096 - 1106   2014.9

Numerical Simulation of a Self-Leveling Experiment Using a Hybrid Method Reviewed International journal

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

Mechanical Engineering Journal   1 ( 4 )   2014.8

Experimental Study and Empirical Model Development for Self-Leveling Behavior of Debris Bed Using Gas-Injection Reviewed International journal

Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Mechanical Engineering Journal   1 ( 4 )   2014.8

Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment Reviewed International journal

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

Proc. of 2014 22nd International Conference on Nuclear Engineering (ICONE22)   2014.7

Numerical Simulation of Gas-Solid Fluidized Beds by Coupling a Fluid-Dynamics Model with the Discrete Element Method Reviewed International journal

@Liancheng Guo, @Koji Morita, @Yoshiharu Tobita

Annals of Nuclear Energy   72   31 - 38   2014.4

Numerical Study on Sedimentation Behavior of Solid Particles Used as Simulant Fuel Debris Reviewed International journal

Md. Shamsuzzaman, Bin Zhang, Tatsuhiro Horie, Fusata Fuke, Tatsuya Matsumoto, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita

Journal of Nuclear Science and Technology   51 ( 5 )   681 - 699   2014.2

Evaluation of Debris Bed Self-Leveling Behavior: A Simple Empirical Approach and its Validations Reviewed International journal

Songbai Cheng, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Annals of Nuclear Energy   63   188 - 198   2014.1

Improved Simulation of a Single Bubble Rising in Stagnant Liquid Using Finite Volume Particle Method Reviewed International journal

Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang

Proc. of 24th International Symposium on Transport Phenomena (ISTP-24)   2013.11

Numerical Simulation of 3D Particulate Flow by Coupling Multi-Fluid Model with Discrete Element Method International journal

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

Proc. of Joint Research Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2013)   2013.10

Developing A Methodological Framework for Extending An Empirical Model to Predict Self-Leveling Behavior of Debris Beds with Non-Spherical Particles Reviewed International journal

Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Proc. of the International Conference on Power Engineering-13 (ICOPE-13)   2013.10

Numerical Simulation of Self-leveling Behavior in Debris Bed by a Hybrid Method Reviewed International journal

GUO LIANCHENG, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21)   2013.7

Experimental Evaluation of Debris Bed Characteristics in Particulate Debris Sedimentation Behaviour Reviewed International journal

Md. Shamsuzzaman, Tatsuhiro Horie, Fusata Fuke, Takayuki Kai, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita

Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21)   2013.7

Experimental Investigation on Self-Leveling Behavior of Debris Beds Using Gas-Injection Reviewed International journal

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yoji Gondai, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Experimental Thermal and Fluid Science   48   2013.7

Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method Reviewed International journal

Yuki Aramaki, Takahito Suzuki, Ichiro Miya, GUO LIANCHENG, Koji Morita

Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21)   2013.7

Recent Knowledge from an Experimental Investigation on Self-Leveling Behavior of Debris Bed Reviewed International journal

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21)   2013.7

Characteristics of Self-Leveling Behavior of Debris Beds in a Series of Experiments Reviewed International journal

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Nuclear Engineering and Technology   45 ( 3 )   323 - 334   2013.6

Empirical Correlations for Predicting the Self-Leveling Behavior of Debris Bed Reviewed International journal

Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita

Nuclear Science and Techniques   24 ( 1 )   2013.2

An Experimental Study on Self-Leveling Behavior of Debris Beds with Comparatively Higher Gas Velocities Reviewed International journal

S. CHENG, H. YAMANO, T. SUZUKI, Y. TOBITA, Y. GONDAI, Y. NAKAMURA, B. ZHANG, T. MATSUMOTO, K. MORITA

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Analysis of Heat-Transfer and Wall-Failure Behaviors in EAGLE-1 In-Pile Test ID1 using Finite Volume Particle Method Reviewed International journal

N. APRIANTI, T. TAKEDA, I. MIYA, L. GUO, K. MORITA

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Particle-Based Simulation of Melt Freezing Behavior in Pin Bundle Reviewed International journal

K. MORITA, T. TAKEDA, W. OHSHIMA, N. APRIANTI, L. GUO

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Numerical Simulation of Bubbling Fluidized Beds by Coupling Multi-Fluid Model with Discrete Element Method Reviewed International journal

L. GUO, K. MORITA, Y. TOBITA

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Experimental Investigation of Debris Sedimentation Behavior on Bed Formation Characteristics Reviewed International journal

M. SHAMSUZZAMAN, T. HORIE, F. FUKE, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, H. TAGAMI, T. SUZUKI, Y. TOBITA

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Validation of the SIMMER-IV Severe Accident Computer Code on Three-Dimensional Sloshing Behavior Reviewed International journal

H. YAMANO, T. SUZUKI, Y. TOBITA, T. MATSUMOTO, K. MORITA

Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8)   2012.12

Numerical Simulation of Three-Phase Flows with Rich Solid Particles by Coupling Multi-Fluid Model with Discrete Element Model Reviewed International journal

L. GUO, K. MORITA, Y. TOBITA

Proc. of 2012 20th International Conference on Nuclear Engineering collocated with ASME 2012 Power Conference (ICONE20-POWER2012)   2012.7

Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III Reviewed International journal

B. ZHANG, T. MATSUMOTO, K. MORITA, H. YAMANO, H. TAGAMI, T. SUZUKI, Y. TOBITA

Proc. of 2012 20th International Conference on Nuclear Engineering collocated with ASME 2012 Power Conference (ICONE20-POWER2012)   2012.7

Fundamental Validation of the Finite Volume Particle Method for 3D Sloshing Dynamics Reviewed International journal

L. GUO, S. ZHANG, K. MORITA, K. FUKUDA

Int. J. Numerical Methods in Fluids   68 ( 1 )   2012.1

Experimental investigation of solid-liquid mixtures freezing behavior in flow channels Reviewed International journal

Md. A.M. SONER, Y. HASEGAWA, S. SEO, Y. HIMURO, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK

Nuclear Engineering and Design   241 ( 10 )   2011.10

3D Simulation of Solid-melt Mixture Flow with Melt Solidification Using a Finite Volume Particle Method Reviewed International journal

R. SN MAHMUDAH, M. KUMABE, T. SUZUKI, L. GUO, K. MORITA

J. Nuclear Science and Technology   48 ( 10 )   2011.10

Experimental Studies and Empirical Models for the Transient Self-Leveling Behavior in Debris Bed Reviewed International journal

S. CHENG, Y. TANAKA, Y. GONDAI, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMONO, T. SUZUKI, Y. TOBITA

J. Nuclear Science and Technology   48 ( 10 )   2011.10

Prevention and Mitigation of Severe Accident Developments and Recriticalities in Advanced Fast Reactor Systems Reviewed International journal

W. MASCHEK, M. FLAD, C.M. BOCCACCINI, S. WANG, F. GABRIELLI, V. KRIVENTSEV, X.N. CHEN, D. ZHANG, K. MORITA

Progress in Nuclear Energy   53 ( 7 )   2011.9

Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method Reviewed International journal

T. SUZUKI, L. GUO, R. SN MAHMUDAH, K. MORITA

Proc. of 19th International Conference on Nuclear Engineering (ICONE-19)   2011.8

Particle Effects on Penetration and Solidification of Flowing Mixed Melts on Metal Structures Reviewed International journal

Md. A.M. SONER, Y. HASEGAWA, T. MATSUMOTO, K. MORITA, W. MASCHEK

J. Nuclear Science and Technology   48 ( 8 )   2011.8

Simulation of Solid-liquid Multiphase Flows with Fuel Relocation and Freezing Behavior in Pin Bundle Geometry Reviewed International journal

Md. A.M. SONER, Y. HASEGAWA, T. MATSUMOTO, K. MORITA, W. MASCHEK

Proc. of 19th International Conference on Nuclear Engineering (ICONE-19)   2011.8

Experimental Investigation of Bubbling in Particle Beds with High Solid Holdup Reviewed International journal

S. CHENG, D. HIRAHARA, Y. TANAKA, Y. GONDAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA

Experimental Thermal and Fluid Science   35 ( 2 )   2011.2

Experimental Investigation on Self-leveling Behavior in Debris Beds Reviewed International journal

B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA

Nuclear Engineering and Design   241 ( 1 )   2011.1

Development of Heat and Mass Transfer Model for Analysis of Material Relocation Phase in Fast Reactors Reviewed International journal

K. MORITA, H. YAMANO, Y. TOBITA

Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010   2010.11

Numerical Simulation of Rheological Behavior in Melting Metal Using Finite Volume Particle Method Reviewed International journal

L. GUO, Y. KAWANO, S. ZHANG, T. SUZUKI, K. MORITA, K. FUKUDA

J. Nuclear Science and Technology   47 ( 11 )   2010.11

3D Simulation of Solid-melt Mixture Flow with Phase Change Using Finite Volume Particle Method Reviewed International journal

R. SN MAHMUDAH, M. KUMABE, W. TORII, I. MIYA, T. TAKEDA, T. SUZUKI, L. GUO, K. MORITA

Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010   2010.11

Experimental Investigation on Self-leveling Behavior in Debris Bed Reviewed International journal

S. CHENG, Y. TANAKA, Y. GONDAI, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA

Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010   2010.11

Experimental Study on Penetration and Freezing Behavior of Solid-liquid Multiphase Flow in Pin Bundle Geometry Reviewed International journal

Md. A.M. SONER, Y. HASEGAWA, S. NAKAYAMA, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK

Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010   2010.11

Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (1) Overview of Evaluation Technology Development Reviewed International journal

Ryodai Nakai, Tohru Suzuki, Kenji Kamiyama, Hiroshi Seino, Kazuya Koyama, Koji Morita

Proc. of 8th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-8)   2010.10

Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code Reviewed International journal

K. MORITA, S. ZHANG, T. ARIMA, S. KOSHIZUKA, Y. TOBITA, H. YAMANO, T. ITO, N. SHIRAKAWA, F. INOUE, H. YUGO, H. OKADA, M. HIMI, Y. YAMAMOTO, E. HIRANO, S. SHIMIZU, M. OUE

Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010   2010.5

3D Simulation of Molten Metal Freezing Behavior Using Finite Volume Particle Method Reviewed International journal

R. SN MAHMUDAH, M. KUMABE, T. SUZUKI, L. GUO, K. MORITA, K. FUKUDA

Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010   2010.5

Numerical Simulation of 3D Liquid Sloshing Motion With Solid Particles Using Finite Volume Particle Method Reviewed International journal

L. GUO, S. ZHANG, K. MORITA, K. FUKUDA

Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010   2010.5

Experimental Investigation of Freezing Behavior of Melt/Solid Particles Mixture on to Metal Structure Reviewed International journal

Md. A.M. SONER, S. SEO, Y. HASEGAWA, Y. HIMURO, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK

Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010   2010.5

Experimental Study of Bubble Behavior in a Two-Dimensional Particle Bed With High Solid Holdup Reviewed International journal

S. CHENG, D. HIRAHARA, Y. TANAKA, Y. GONDAI, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANAO, T. SUZUKI, Y. TOBITA

Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010   2010.5

Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code Reviewed International journal

S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMAMOTO

J. Power and Energy Systems   2010.2

Validation for Multi-physics Simulation of Core Disruptive Accidents in Sodium-cooled Fast Reactors by COMPASS Code Reviewed International journal

S. KOSHIZUKA, K. MORITA, T. ARIMA, S. ZHANG, Y. TOBITA, H. YAMANO, T. ITO, M. NAITO, N. SHIRAKAWA, H. OKADA, Y. UEHARA, Y. NAGAMINE, Y. YAMAMOTO, M. HIMI, E. HIRANO, S. SHIMIZU, M. OUE

Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009   2009.9

Simulation of Rheological Behavior During Melting Process Using Moving Particle Method Reviewed International journal

L. GUO, Y. KAWANO, S. ZHANG, K. MORITA, K. FUKUDA

Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009   2009.9

Criteria for Occurrence of Self-Leveling in the Debris Bed Reviewed International journal

B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA

Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009   2009.9

R&D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology (3) Thermal Hydraulics Models of COMPASS Code and Experimental Analyses Reviewed International journal

Y. YAMAMOTO, E. HIRANO, M. OUE, S. SHIMIZU, N. SHIRAKAWA, S. KOSHIZUKA, K. MORITA, H. YAMANO, Y. TOBITA

Proc. of 17th International Conference on Nuclear Engineering (ICONE-17), Brussels, Belgium, July 12-16, 2009   2009.7

R&D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology (4) Development of a Computational Framework on Fluid-solid Mixture Flow Simulations for the COMPASS Code Reviewed International journal

S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMANOTO

Proc. of 17th International Conference on Nuclear Engineering (ICONE-17), Brussels, Belgium, July 12-16, 2009   2009.7

Safety Concepts of the 400MWth-Class EFIT Accelerator Driven Transmuter and Considerations for Further Developments Reviewed International journal

W. MASCHEK, X.-N. CHEN, P. LIU, F. GABRIELLI, A. RINEISKI, M. FLAD, S. WANG, G. RIMPAULT, F. DELAGE, K. MORITA, M. RAHMAN, T. HINO

Proc. of 14th International Conference on Emerging Nuclear Energy Systems (ICENES 2009), June 29-July 3, 2009, Ericeira, Portugal   2009.6

Analyses of Transients for 400MWth-Class EFIT Accelerator Driven Transmuter with the SIMMER-III Code Reviewed International journal

P. LIU, X-N. CHEN, F. GABRIELLI, M. FLAD, W. MASCHEK, A. RINEISKI, S. WANG, K. MORITA, M.M. RAHMAN, Y. EGE

Proc. of International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators (AccApp 2009), May 4-8 2009, Vienna, Austria   2009.5

Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (1) Overview of Evaluation Methodology Development Reviewed International journal

R. NAKAI, T. SUZUKI, H. YAMANO, H. SEINO, H. ISHIKAWA, K. KAMIYAMA, K. KOYAMA, K. MORITA

Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09), May 11-15, 2009, Tokyo, Japan   2009.5

COMPASS Code Development and Validation: A Multi-Physics Analysis of Core Disruptive Accidents in Sodium-Cooled Fast Reactors Using Particle Methods Reviewed International journal

S. KOSHIZUKA, J. LIU, K. MORITA, T. ARIMA, S. ZHANG, Y. TOBITA, H. YAMANO, T. ITO, M. NAITOH, N. SHIRAKAWA, S. HOSODA, Y. UEHARA, Y. YAMAMOTO, H. KOZAKAI, M. HIMI, E. HIRANO, S. SHIMIZU, M. OUE

Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP'09)   2009.5

Improvement of Basic Fluid Dynamics Models for the COMPASS Code Reviewed International journal

S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMAMOTO

J. Power and Energy Systems   2009.3

Investigation of Molten Metal Penetration and Freezing Behavior in a Seven-Pin Channel Reviewed International journal

M. KABIR HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK

Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan   2008.11

Experimental Study of Self-Leveling Behavior in Debris Bed Reviewed International journal

B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA

Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan   2008.11

Simulation of Single Bubble Rising up in Stagnant Liquid Pool with Finite Volume Particle Method Reviewed International journal

S. ZHANG, L. GUO, K. MORITA, K. FUKUDA, N. SHIRAKAWA, Y. YAMAMOTO

Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan   2008.11

Transient Behavior of Particle Movement in a Boiling Debris Bed Reviewed International journal

T. MATSUMOTO, Y. KONO, T. HARADA, D. HIRAHARA, K. MORITA, K. FUKUDA

Proc. of the Seventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), October 5-9, 2008, Seoul, Korea   2008.10

Code development for multi-physics and multi-scale analysis of core disruptive accidents in fast reactors using particle methods Reviewed International journal

S. Koshizuka, K. Morita, T. Arima, S. Zhang, Y. Tobita, H. Yamano, T. Ito, N. Shirakawa, M. Naito, H. Okada, Y. Uehara, Y. Nagamine, Y. Yamamoto, M. Himi, E. Hirano, S. Shimizu, M. Oue

Proc. of 16th Pacific Basin Nuclear Conference (PBNC-16), October 13-18, 2008, Aomori, Japan   2008.10

The SIMMER Safety Code System and its Validation Efforts for Fast Reactor Application Reviewed International journal

W. MASCHEK, A. RINEISKI, M. FLAD, H. YAMANO, Y. TOBITA, S. FUJITA, T. SUZUKI, K. KAMIYAMA, S. PIGNY, T. CADIOU, K. MORITA, G. BANDINI

Proc. of the International Conference on the Physics of Reactors 2008 (PHYSOR'08), Interlaken, Switzerland, Sept. 14-19, 2008   2008.9

Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling Reviewed International journal

S. WANG, M. FLAD, W. MASCHEK, P. AGOSTINI, D. PELLINI, G. BANDINI, T. SUZUKI, K. MORITA

Progress in Nuclear Energy   2008.8

Report on Intermediate Results of the IAEA CRP on ‘Studies Of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste’ Reviewed International journal

W. MASCHEK, A. STANCULESCU, B. ARIEN, Y. BAI, Ch. CHABERT, A.A. CHEBESKOV, X. CHEN, D.F. da CRUZ, V. DEKOUSSAR, K. DEVAN, S. DULLA, V. GOPALAKRISHNAN, O. FEYNBERG, R. HARISH, V. IGNATIEV, J. KÓPHÁZI, J. LI, E. MALAMBU, P. MOHANAKRISHNAN, K. MORITA, G. PANDIKUMAR, Y. PENELIAU, P. RAVETTO, A. RINEISKI, M. SCHIKORR, R. SRIVENKATESAN, V. SUBBOTIN, A. SURENKOV, M. SZIEBERTH, S. TACZANOWSKI, K. TUČEK, P. VERTES, M. VOROTYNTSEV, J. UHLÍŘ, H. WIDER, Y. WU, R. ZAKIROV, S. ZHEN

Energy Conversion and Management   2008.7

R&D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology (2) Development and Verification of Thermo-Hydraulics Module of the COMPASS Code Reviewed International journal

Yuichi YAMANOTO, Etsujo HIRANO, Masaya OUE, Sensuke SHIMIZU, Noriyuki SHIRAKAWA, Seiichi KOSHIZUKA, Koji MORITA

Proc. 16th Int. Conf. on Nuclear Engineering, Orlando, Florida, US, May 11-15, 2008   2008.5

R&D of the Next Generation Safety Analysis Methods for Fast Reactors with New Computational Science and Technology (3) Improvement of Basic Fluid Dynamics Models for the COMPASS Code Reviewed International journal

Shuai ZHANG, Koji MORITA, Noriyuki SHIRAKAWA, Yuichi YAMANOTO

Proc. 16th Int. Conf. on Nuclear Engineering, Orlando, Florida, US, May 11-15, 2008   2008.5

Code Development for Core Disruptive Accidents in Sodium-Cooled Fast Reactors Reviewed International journal

Seiichi KOSHIZUKA, Jie LIU, Koji MORITA, Tatsumi ARIMA, Shuai ZHANG, Yoshiharu TOBITA, Hidemasa YAMANO, Takahiro ITO, Masanori NAITOH, Noriyuki SHIRAKAWA, Seigo HOSODA, Yasushi UEHARA, Yuichi YAMANOTO, Masashi HIMI, Hiroshi KOZAKAI, Etsujo HIRANO, Sensuke SHIMIZU, Masaya OUE

Proc. of IAEA Topical Meeting on Advanced Safety Assessment Methods for Nuclear Reactors, Daejon, Korea, October 30 - Nomebmebr 2, 2007   2007.10

Experimental Investigation of Molten Metal Freezing on to a Structure Reviewed International journal

M. Mizanur RAHMAN, Tomohiko HINO, Koji MORITA, Tatsuya MATSUMOTO, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK

Experimental Thermal and Fluid Science   2007.10

The IAEA CRP on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste Reviewed International journal

W. MASCHEK, A. STANCULESCU, B. ARIEN, Y. BAI, Ch. CHABERT, A.A. CHEBESKOV, X. CHEN, D.F. da CRUZ, V. DEKOUSSAR, K. DEVAN, S. DULLA, V. GOPALAKRISHNAN, O. FEYNBERG, R. HARISH, V. IGNATIEV, J. KÓPHÁZI, J. LI, E. MALAMBU, P. MOHANAKRISHNAN, K. MORITA, G. PANDIKUMAR, Y. PENELIAU, P. RAVETTO, A. RINEISKI, M. SCHIKORR, R. SRIVENKATESAN, V. SUBBOTIN, A. SURENKOV, M. SZIEBERTH, S. TACZANOWSKI, K. TUČEK, P. VERTES, M. VOROTYNTSEV, J. UHLÍŘ, H. WIDER, Y. WU, R. ZAKIROV, S. ZHEN

Proc. of International Conference GLOBAL 2007, Boise, Idaho, September 9-13, 2007   2007.9

A New Algorithm for Surface Tension Model in Moving Particle Methods Reviewed International journal

Shuai ZHANG, Koji MORITA, Kenji FUKUDA, Noriyuki SHIRAKAWA

Int. J. Numerical Methods in Fluids   2007.9

First Safety Analyses for an EFIT Type Accelerator Driven Transmuter Reviewed International journal

Ping Liu, Xuenong Chen, Andrei Rineiski, Claudia Matzerath Boccaccini, Fabrizio Gabrielli, Werner Maschek, Koji Morita, Fosco Bianchi

Proc. of the Eighth International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'07), Pocatello, ID, July 30-August 2, 2007   2007.7

Report on Intermediate Results of the IAEA CRP on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste' Reviewed International journal

W. MASCHEK, A. STANCULESCU, B. ARIEN, Y. BAI, Ch. CHABERT, A.A. CHEBESKOV, X. CHEN, D.F. da CRUZ, V. DEKOUSSAR, K. DEVAN, S. DULLA, V. GOPALAKRISHNAN, O. FEYNBERG, R. HARISH, V. IGNATIEV, J. KÓPHÁZI, J. LI, E. MALAMBU, P. MOHANAKRISHNAN, K. MORITA, G. PANDIKUMAR, Y. PENELIAU, P. RAVETTO, A. RINEISKI, M. SCHIKORR, R. SRIVENKATESAN, V. SUBBOTIN, A. SURENKOV, M. SZIEBERTH, S. TACZANOWSKI, K. TUČEK, P. VERTES, M. VOROTYNTSEV, J. UHLÍŘ, H. WIDER, Y. WU, R. ZAKIROV, S. ZHEN

Proc. of 13th International Conference on Emerging Nuclear Energy Systems (ICENES 2007), Istanbul, Turkey, June 3-8, 2007   2007.6

Critical Parameters and Equation of State for Heavy Liquid Metals Reviewed International journal

Koji MORITA, Vitaly SOBOLEV, Michael FLAD

J. Nuclear Materials   2007.5

SIMMER-III: A coupled Neutronics-Thermohydraulics Computer Code for Safety Analysis Reviewed International journal

Hidemasa Yamano, Yoshiharu Tobita, Satoshi Fujita, Tohru Suzuki, Kenji Kamiyama, Koji Morita, Werner Maschek, Sylvain Pigny

Proc. 15th Int. Conf. on Nuclear Engineering, Nagoya, Japan, April 22-26, 2007   2007.4

Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling Reviewed International journal

S. Wang, M. Flad, W. Maschek, P. Agostini, D. Pellini, T. Suzuki, K. Morita

Proc. the 2nd COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, November 26 - 30, 2006, Yokohama, Japan   2006.11

Condensation of a Large-Scale Bubble in Subcooled Liquid: Experimental Verification of the SIMMER-III Code Reviewed International journal

Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Ikken SATO, Hidemasa YAMANO

Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006   2006.11

Multi-Physics and Multi-Scale Simulation for Core Disruptive Accidents in Fast Breeder Reactors Reviewed International journal

Seiichi KOSHIZUKA, Jie LIU, Koji MORITA, Tatsumi ARIMA, Yoshiharu TOBITA, Hidemasa YAMANO, Takahiro ITO, Noriyuki SHIRAKAWA, Seigo HOSODA, Kazuhiro ARAKI, Masanori NAITOH, Yuichi YAMANOTO, Hiroshi KOZAKAI, Masashi HIMI, Etsujo HIRANO, Sensuke SHIMIZU, Masaya OUE

Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006   2006.11

Experimental Simulation of Molten Metal Freezing Behavior onto a Structure with a Reactor Safety Analysis Code, SIMMER-III Reviewed International journal

M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHECK

Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006   2006.11

Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels Reviewed International journal

Werner Maschek, Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Claudia Matzerath Boccaccini, Magnus Mori, Koji Morita

Nuclear Instruments and Methods in Physics Research A   2006.6

Equation of State for Heavy Liquid Metal Targets Reviewed International journal

K.Morita, V.Sobolev, M. Flad

Proc. E-MRS 2006 Spring Meeting, Nice, France, May 29-June 2, 2006   2006.5

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments Reviewed International journal

Y. Tobita, Sa. Kondo, H. Yamano, K. Morita, W. Maschek, P. Coste, T. Cadiou

Nuclear Technology   2006.3

Development of an Analytical Method of Evaluation of Best-Mixed Electric Power generating Systems reflecting Public Preferences and of Willingness-to-Pay for External Values - For better social approval of the 'Nuclear Power' - Reviewed International journal

Kenji Fukuda, Narumi Shikasyo, Tastuya Matsumoto, Koji Morita

Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005   2005.10

Analysis of Transients for an IAEA Benchmark on Accelerator Driven Transmuters with Fertile-Free Fuels Reviewed International journal

Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Clausia Matzerath Boccaccini, Werner Maschek, Koji Morita

Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005   2005.10

Analysis of Transients and Severe Accidents in Accelerator Driven Transmuters (ADTs) of the 800 MWth Class with Fertile-Free Fuels Reviewed International journal

Xue-Nong Chen, Tohru Suzuki, Andrei Rineiski, Magnus Mori, Clausia Matzerath Boccaccini, Werner Maschek, Koji Morita

Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005   2005.10

SIMMER-III and SIMMER-IV Safety Code Development for Reactors with Transmutation Capability Reviewed International journal

W. MASCHEK, A. RINEISKI, T. SUZUKI, S. WANG, Mg. MORI, E. WIEGNER, D. WILHELM, F. KRETZSCHMAR, Y. TOBITA, H. YAMANO, S. FUJITA, P. COSTE, S. PIGNY, A. HENRIQUES, T. CADIOU, K. MORITA, G. BANDINI

Mathematics and Computation, Supercomputing, Reactor Physics and Biological Applications, Palais de Papes, Avignon, France, September 12-15, 2005, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2005)   2005.9

Analysis of transients for an 800MWth-class accelerator driven transmuter with fertail-free fuels Reviewed International journal

Werner Maschek, Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Clausia Matzerath Boccaccini, Magnus Mori, Koji Morita

The Seventh International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp05), Venice, Italy, August 29-September 1, 2005   562 ( 2 )   863 - 866   2005.8

Thermodynamic Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis Reviewed International journal

Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano

Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005   2005.5

A Review on Safety Issues and Analysis Tools for Accelerator Driven Systems and Transmuters Reviewed International journal

Wernar Maschek, Xue-Nong Chen, Tohru Suzuki, Andrei Rineiski, Claudia Matzerath Boccaccini, Magnus Mori, Koji Morita

Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005   2005.5

Simulation of the Incompressible Flows with the MPS Method Reviewed International journal

Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa

Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005   2005.5

Simulation of Multi-phase Flows with Solid Particle Bed in a Water Pool Reviewed International journal

Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita

Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005   2005.5

社会的選好に適合する電源構成と支払い意志額の解析手法の開発 (Development of Analytical Evaluation of Best-mixed Power Generation Systems and Willingness-to-pay reflecting Plublic Preferences) Reviewed

四ヶ所成美, 赤坂　亮, 松元達也, 守田幸路, 福田研二

エネルギー・資源   2004.11

Improvement of a Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behaviors Reviewed International journal

K. Morita, T. Matsumoto, K. Fukuda, Y. Tobita, H. Yamano, I. Sato,

6th Int. Conf. on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-6), Nara, Oct. 4-8, 2004   2004.10

Monte-Carlo/Simmer-III Reactivity Coefficients Calculations for the SuperCritical Water Fast Reactor Reviewed International journal

M. Mori, W. Maschek, E. Laurien, K. Morita

Proceedings of GLOBAL 2003 - Advanced Nuclear Energy and Fuel Cycle Systems, New Orleans, LA, November 16-21, 2003   2003.11

Monte-Carlo/Simmer-III Reactivity Coefficients Calculations for the SuperCritical Water Fast Reactor Reviewed International journal

Magnus Mori, Werner Maschek, Eckart Laurien, Koji Morita

Proceedings of GLOBAL 2003   2003.11

Evaluation of Cooling Capability in a Heated Narrow Flow Passage Reviewed International journal

Akihiro Uchibori, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda

J. Nuclear Science and Technology   40 ( 10 )   796 - 806   2003.10

Behavior of Transmuter Fuels of Accelerator Driven Systems under Severe Accident Conditions Reviewed International journal

W. Maschek, T. Suzuki, X. Chen, Mg. Mori, C. Matzerath Boccaccini, M. Flad, K.Morita

Proceedings of GENES4/ANP2003   2003.9

Investigation into Coolability by Two-Phase Flow in Narrow Flow Passages Reviewed International journal

A. Uchibori, Y. Ishimaru, M. Yamashita, T. Matsumoto, R. Akasaka, K. Morita, K. Fukuda

Proceedings of the Eleventh International Conference on Nuclear Engineering (ICONE-11)   2003.4

Generalized Modeling of Multicomponent Vaporization/Condensation Phenomena for Multiphase-Flow Analysis Reviewed International journal

K. Morita, K. Fukuda, Y. Tobita, Sa. Kondo, T. Suzuki, W. Maschek

Proceedings of the German-Japanese Workshop on Multi-Phase Flow, Karlsruhe, Germany, August 26-28, 2002, Forschungszentrum Karlsruhe, FZKA 6759   2003.3

Analysis of severe transient scenarios and proposals for safety improvements for ADS transmuters with dedicated fuel Reviewed International journal

W. Maschek, A. Rineiski, M. Flad, K. Morita, P. Coste

Nuclear Technology   2003.1

An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference Reviewed International journal

R. Akasaka, N. Shikasho, K. Morita, K. Fukuda

Greenhouse Gas Control Technologie   1019 - 1024   2003.1

An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference Reviewed International journal

R. Akasaka, N. Shikasho, K. Morita, K. Fukuda

Greenhouse Gas Control Technologies, J. Gale and Y. Kaya (Eds.), Elsevier Science, 2003   1019 - 1024   2003.1

Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions. Applications of artificial neural network Reviewed International journal

G. Su, K. Morita, K. Fukuda, M. Pidduck, D. Jia, J. Miettinen

Nuclear Engineering and Design   220 ( 1 )   17 - 35   2003.1

Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Extended verification using multi-bubble condensation experiment Reviewed International journal

T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda

Nuclear Engineering and Design   220 ( 3 )   240 - 254   2003.1

Applications of Artificial Neural Network for the Prediction of Flow Boiling Curves Reviewed International journal

G. Su, K. Fukuda, K. Morita, M. Pidduck, D. Jia, T. Matsumoto, R. Akasaka

J. Nuclear Science and Technology   39 ( 11 )   1190 - 1198   2002.11

The Development of SIMMER-III, an Advanced Computer Program for LMFR Safety Analysis Reviewed International journal

Y. Tobita, S. Kondo, H. Yamano, S. Fujita, K. Morita, W. Maschek, P. Coste, S. Pigny, J. Louvet, T. Cadiou

A Joint IAEA/NEA Technical Meeting on the Use of Computational Fluid Dynamics Codes for Safety Analysis of Reactor Systems (including Containment), Pisa, Italy, November 11-13, 2002   2002.11

Numerical Study on Cooling Mechanism in Hemispherical Narrow Gap for In-vessel Molten Core Retention Reviewed International journal

A. Uchibori, T. Matsumoto, K. Morita, K. Fukuda

Proceedings of the Third Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-3), Kyeongju, Korea, October 13-16, 2002   2002.10

An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference Reviewed International journal

R. Akasaka, N. Shikasho, K. Morita, K. Fukuda

Proceeding of the Sixth International Conference on Greenhouse Gas Control Technologies (GHGT-6), Kyoto, October 2002   2002.10

Applications of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux Reviewed International journal

G. Su, K. Fukuda, D. Jia, K. Morita

J. Nuclear Science and Technology   2002.5

Applications of Artificial Neural Network for the Prediction of Pool Boiling Curves Reviewed International journal

G. Su, K. Fukuda, K. Morita

Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002   2002.4

Advanced Modeling of Multicomponent Vaporization/Condensation Phenomena for a Reactor Safety Analysis Code SIMMER-III Reviewed International journal

K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo

Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002   2002.4

Applicability of Modified Drift Flux Model for Bubbly Flow in 2-D/3-D Rectangular Box with Various Kinds of Obstacles Reviewed International journal

T. Matsumoto, A. Uchibori, R. Akasaka, T. Seki, S. Kaminishi, K. Morita, K. Fukuda

Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002   2002.4

Numerical Prediction of Cooling Capability in Hemispherical Gap Flow Passage for In-vessel Core Retention Reviewed International journal

A. Uchibori, K. Fukuda, K. Morita, T. Matsumoto

Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002   2002.4

Safety Improvements for ADS Transmuters with Dedicated Fuel Reviewed International journal

W. MASCHEK, A. RINEISKI, S. WANG, M. FLAD, K. MORITA

Proc. of the American Nuclear Society Fifth International Topical Meeting on Nuclear Applications of Accelerator Technology – Accelerator Applications/Accelerator-Driven Transmutation Technology and Applications (AccApp/ADTTA'01), Reno, NV, USA, November 11-15, 2001.   2001.11

Inherent and Passive Safety Measures in Accelerator Driven Systems: A Safety Strategy for ADS Reviewed International journal

W. Maschek, A. Rineiski, K. Morita, M. Flad

Proceedings of the International Conference on Back-End of the Fuel Cycle: From Research to solutions (GLOBAL 2001), Paris, France, September 9-13, 2001   2001.9

The Effect of Bubble Size on the Radial Distribution of Void Fraction in Two-Phase Flow in a Circular Tube Reviewed International journal

H. Horie, N. Shirakawa, Y. Tobita, K. Morita, Sa. Kondo

J. Nuclear Science and Technology   38 ( 9 )   711 - 720   2001.9

Applicability of Modified Drift Flux Model for 3-D Channel Bubbly Flow with a Rod Inserted Reviewed International journal

K. Fukuda, T. Matsumoto, N. Kamesako, A. Uchibori, R. Akasaka, K. Nakagawa, K. Morita, A. Hotta

PVP-Vol. 424-1, Computational Technologies for Fluids/Thermal/Structural/Chemical Systems with Industrial Applications -2001-, The 2001 ASME Pressure Vessels and Piping Conference, Atlanta, Georgia, July 22-26, 2001   2001.6

Numerical Study on Thermal Hydraulic Phenomena in a Hemispherical Gap under Core Meltdown Accident Reviewed International journal

A. Uchibori, K. Fukuda, K. Morita, T. Matsumoto

PVP-Vol. 424-1, Computational Technologies for Fluids/Thermal/Structural/Chemical Systems with Industrial Applications -2001-, The 2001 ASME Pressure Vessels and Piping Conference, Atlanta, Georgia, July 22-26, 2001   2001.6

Mechanistic SIMMER-III Analyses of Severe Transients in Accelerator Driven Systems (ADS) Reviewed International journal

K. Morita, A. Rineiski, E. Kiefhaber, W. Maschek; M. Flad, G. Rimpault, P. Coste, S. Pigny, Sa. Kondo, Y. Tobita, S. Fujita

Proceedings of the Ninth International Conference on Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001   2001.4

ドリフトフラックスモデルの多次元多成分混相流解析への応用 Reviewed

守田 幸路、児玉 祐二、藤本 登、中川 清、饒 燕飛、楊 瑞昌、福田 研二

日本原子力学会誌   2000.12

SIMMER-III Code Development for Analyzing Transients and Accidents in Accelerator Driven Systems (ADS) Reviewed International journal

W. Maschek, A. Rineiski, K. Morita, E. Kiefhaber, G. Buckel, M. Flad, P. Coste, S. Pigny, G. Rimpault, J. Louvet, T. Cadiou,Sa. Kondo, Y. Tobita, T. Suzuki, H. Yamano, S. Fujita

Proceeding of the fourth International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp00), Washington D.C., US, Nov. 13-15, 2000.   2000.11

Safety Analyses for ADS Cores with Dedicated Fuel and Proposals for Safety Improvements Reviewed International journal

W. Maschek, A. Rineiski, K. Morita, G. Mühing, M. Flad, R.J.M. Konings

Proceeding of IAEA technical Commitee Meeting on Core Physics and Engineering Aspects of Engineering Nuclear Energy Systems for Energy generation and Transmutation, Argonne, IL, Nov. 28 - Dec. 1, 2000   2000.11

Analytical and Experimental Studies of Two Phase Flows in 2-D rectangular Box with Obstacles inserted Reviewed International journal

T. Matsumoto, N. Kamesako, T. Seki, A. Uchibori, R. Akasaka, N. Fujimoto, K. Nakagawa, K. Morita, K. Fukuda

Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000   2000.10

Current Status and Application of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis Reviewed International journal

Y. Tobita, Sa. Kondo, H. Yamano, S. Fujita, K. Morita, W. Maschek, J. Louvet, P. Coste, S. Pigny

Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000   2000.10

Numerical Study on Thermal Hydraulic Phenomena in a Hemispherical gap under Core Meltdown Accident Reviewed International journal

A. Uchibori, T. Matsumoto, K. Morita, K. Fukuda

Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000   2000.10

SIMMER-III Code Development for Accelerator Driven Systems (ADS) Reviewed International journal

W. Maschek, A. Rineiski, E. Kiefhaber, G. Buckel, K. Morita, M. Flad, P. Coste, S. Pigny, J. Louvet, T. Cadiou, G. Rimpault, S. Kondo, Y. Tobita, T. Suzuki

Proceedongs of the 6th International CAPRA/CADRA Seminar, Newby Bridge, Great Britain, June 26-28, 2000.   2000.6

障害物の存在する系の二次元気液二相流の数値解析 Reviewed

赤坂 亮、関 俊徳、内堀 昭寛、亀迫 望、守田 幸路、松元 達也、堀田 亮年、福田 研二

九州大学工学集報   2000.5

Application of the Drift Flux Model to Gas-Liquid Two-phase Flows with Obstacles Reviewed International journal

N. Fujimoto, N. Kamesako, T. Dohmen, K. Morita, K. Fukuda, A. Hotta, R.C. Yang

Proceedings of the Eighth International Conference on Nuclear Engineering (ICONE-8), Baltimore, MD USA, April 2-6, 2000   2000.4

相変化を伴うヘリウムIIの二次元熱流動特性に関する基礎的研究 Reviewed

野田 貴史、饒 燕飛、藤本 登、守田 幸路、福田 研二

九州大学工学集報   2000.1

我が国における原子力発電のエネルギー安全保障と社会的受容性等に関する外部効果の経済評価 Reviewed

藤本 登、守田 幸路、福田 研二

九州大学工学集報   2000.1

A Study on the Effect of Bubble Size on the Radial Distribution of Void Fraction in Two-Phase Flow in a Tube Reviewed International journal

H. Horie, N. Shirakawa, Y. Tobita, K. Morita

Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999   1999.4

Evaluation of CDA Energetics in the Prototype LMFBR with Latest Knowledge and Tools Reviewed International journal

Y. Tobita, K. Morita, K. Kawada, H. Niwa, N. Nonaka

Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999   1999.4

Current Status and Validation of the SIMMER-III LMFR Safety Analysis Code Reviewed International journal

Sa. Kondo, Y. Tobita, K. Morita, D. J. Brear, K. Kamiyama, H. Yamano, S. Fujita, W. Maschek, E. A. Fischer, E. Kiefhaber, G. Buckel, E. Hesserschwerdt, P. Coste, S. Pigny

Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999   1999.4

Applications of the SIMMER-III Fast Reactor Safety Analysis Code to Thermal Interactions of Melts with Sodium and Water Reviewed International journal

K. Morita, Sa. Kondo, Y. Tobita, W. Maschek, M. Flad, G. Arnecke, P. Coste

Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999   1999.4

細管内における超流動ヘリウムの一次元流動伝熱解析に関する研究 Reviewed

高松邦吉、藤本 登、守田 幸路、福田 研二

低温工学   1999.1

SIMMER-III Analyses of Enhanced Fuel Removal Processes under Core Disruptive Accident Conditions Reviewed International journal

W. Maschek, K. Morita, M. Flad

Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6), San Diego, California, May 10-14, 1998   1998.5

SIMMER-III Applications to Fuel-Coolant Interactions Reviewed International journal

K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear

Proceedings of the OECD/CSNI Specialists Meeting on Fuel-Coolant Interactions, Tokai-mura, Japan, May 19-21, 1997, JAERI-Conf 97-011 (Part II) , January 1998   1998.1

シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究

#高西航平， #Md. Iqbal Hosan， @劉 維， @守田幸路， @中村康一， @金井大造

日本原子力学会九州支部第42回研究発表講演会  2023.12 

体積加熱による球形粒子ベッドの熱伝達挙動に関する実験的研究

#温 俊朗， #鎌田 悠斗， #横山 貢成， @松元 達也， @劉 維， @守田 幸路, @今泉 悠也， @田上 浩孝， @松場 賢一， @神山 健司

日本原子力学会九州支部第42回研究発表講演会  2023.12 

集合体型受動的炉停止デバイス燃料ピンにおける溶融金属燃料落下挙動の粒子法シミュレーション

#十河宏考， @劉 維， @守田幸路

日本原子力学会九州支部第42回研究発表講演会  2023.12 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究

@山野 秀将, @高井 俊秀, @江村 優軌, @東 英生, @福山 博之, @守田 幸路, @中村 勤也, @Ahmed Zeeshan, @Pellegrini Marco, @西 剛史

日本原子力学会「2023年秋の大会」  2023.9 

シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究

#栫 明宏、#古賀 瑞樹、@劉 維、@守田 幸路、@中村 康一、@金井 大造

日本原子力学会「2023年秋の大会」  2023.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (35) 電磁浮遊法によるその場観察と急冷法を組み合わせた 14, 17mass%B4C 含有 SUS316L の凝固過程の解明

@相楽 洋、@川島 正俊、@守田 幸路、@劉 維、@有馬 立身、@有田 裕二、@佐藤 勇、@松浦 治明、@関尾 佳弘

日本原子力学会「2023年秋の大会」  2023.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (34) 黒体放射型超高温熱分析法による 14, 17mass%B4C 含有 SUS316L の溶融挙動

@川島 正俊、@相楽 洋、@守田 幸路、@劉 維、@有馬 立身、@有田 裕二、@佐藤 勇、@松浦 治明、@関尾 佳弘

日本原子力学会「2023年秋の大会」  2023.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (32) プロジェクト全体概要及び令和4年度までの進捗

@守田 幸路、@劉 維、@有馬 立身、@有田 裕二、@佐藤 勇、@松浦 治明、@関尾 佳弘、@相楽 洋、@川島 正俊

日本原子力学会「2023年秋の大会」  2023.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究：プロジェクト全体概要及び令和4年度までの進捗

@山野 秀将, @高井 俊秀, @江村 優軌, @福山 博之, @西 剛史, @守田 幸路, @中村 勤也, @Pellegrini Marco

日本機械学会2023年度年次大会  2023.9 

Preliminary Analysis of Severe Accident in Sodium-Cooled Fast Reactor Using Eutectic Reaction Model of Boron-Carbide Control-Rod Material International conference

@Hidemasa Yamano, @Koji Morita

20th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20)  2023.8 

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (1) Safety Analysis of Device-loaded Cores with Different Fuel Materials International conference

@Koji Morita, @Wei Liu, @Tatsumi Arima, @Yuji Arita, @Isamu Sato, @Yoshihiro Sekio, @Hiroshi Sagara, @Masatoshi Kawashima

The 30th International Conference on Nuclear Engineering (ICONE30)  2023.5 

Development of a Simplified One-Dimensional CDA Bubble Model for Source Term Evaluation International conference

#Zeren Zou, @Koji Morita, @Wei Liu

The 30th International Conference on Nuclear Engineering (ICONE30)  2023.5 

A Large-Scale Particle-Based Simulation of Heat And Mass Transfer Behavior in EAGLE ID1 In-Pile Test International conference

#Ting Zhang, #Yao Yao, @Koji Morita, @Xiaoxing Liu, @Wei Liu, @Yuya Imaizumi, @Kenji Kamiyama

The 30th International Conference on Nuclear Engineering (ICONE30)  2023.5 

Experimental Study on Accident Source Terms Transport and Deposition Behavior in Nuclear Power Plants International conference

#Md. Iqbal Hosan, #Mizuki Koga, #Akihiro Kakoi, @Koji Morita, @W. LIU, @Xu Cheng

The 30th International Conference on Nuclear Engineering (ICONE30)  2023.5 

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: (2) A study on Selecting Candidate Fuel Materials for the Basic Device Specifications International conference

@Hiroshi Sagara, @Masatoshi Kawashima, @Koji Morita, @Wei Liu, @Tatsumi Arima, @Yuji Arita, @Isamu Sato, @Yoshihiro Sekio

The 30th International Conference on Nuclear Engineering (ICONE30)  2023.5 

Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (1) Current Status of Overall Project Progress International conference

@Koji Morita, @Wei Liu, @Tatsumi Arima, @Yuji Arita, @Isamu Sato, @Yoshihiro Sekio, @Hiroshi Sagara, @Masatoshi Kawashima

International Symposium on Zero-Carbon Energy Systems  2023.1 

Development of a Passive Safety Shutdown Device to Prevent Core Damage Accidents in Fast Reactors (2) Performance of the Device in Reactivity Control and Nuclear Material Management International conference

@Hiroshi Sagara, @Masatoshi Kawashima, @Koji Morita, Wei Liu, @Tatsumi Arima, @Yuji Arita, @Isamu Sato, @Haruaki Matsuura, @Yoshihiro Sekio

International Symposium on Zero-Carbon Energy Systems  2023.1 

Development and validation of a simplified CDA bubble model

#Zeren ZOU, @Koji MORITA , @Wei LIU

日本原子力学会九州支部第41回研究発表講演会  2022.12 

Analytical Study on Mechanism of Heat Transfer from Molten Pool to Duct Wall in EAGLE ID1 In-pile Test

#Yao Yao, #Ting Zhang, @Koji Morita, @Xiaoxing Liu, @Wei Liu, @Yuya Imaizumi, @Kenji Kamiyama

日本原子力学会九州支部第41回研究発表講演会  2022.12 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 ーデバイス集合体の候補仕様選択とプラントにおける核不拡散性の検討ー

@川島 正俊、@相楽 洋、@守田 幸路

第43回日本核物質管理学会年次大会  2022.11 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (7)2021年度までのプロジェクト全体進捗概要

@守田 幸路、@劉 維、@有馬 立身、@有田 裕二、@佐藤 勇、@松浦 治明、@関尾 佳弘、@相楽 洋、@川島 正俊

日本原子力学会「2022年秋の大会」  2022.9 

受動的炉停止デバイスにおける模擬燃料合金材料の物性評価

@王　浩キン、@佐藤　勇、@守田 幸路

日本原子力学会「2022年秋の大会」  2022.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (9)可視化試験によるデバイス内燃料移動挙動の基礎評価

@関尾 佳弘、@佐藤 勇、@川島 正俊、@守田 幸路

日本原子力学会「2022年秋の大会」  2022.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (10)デバイス効果を強化するデバイス集合体基本仕様の選定

@相楽 洋、@守田 幸路、@川島 正俊、@有馬 立身、@劉 維、@有田 裕二、@佐藤 勇

日本原子力学会「2022年秋の大会」  2022.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (8)模擬燃料材料及び可溶栓材料の選択と物性評価の進捗

@有馬 立身、#住吉 壮斗、@守田 幸路、@佐藤 勇、@王　浩キン、@有田 裕二、@安藤 慧、@宮部 拓

日本原子力学会「2022年秋の大会」  2022.9 

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device International conference

@Koji Morita, @Wei Liu, @Tatsumi Arima, @Yuji Arita, @Isamu Sato, @Yoshihiro Sekio, @Hiroshi Sagara, @Masatoshi Kawashima

The 2022 29th International Conference on Nuclear Engineering (ICONE29)  2022.8 

シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究 (2)矩形貫通部におけるエアロゾル移行挙動に関する実験的研究

#古賀 瑞樹， #宇和田 尚悟, @劉 維, @守田 幸路, @中村 康一, @金井 大造

日本原子力学会「2022年春の年会」  2022.3 

受動的炉停止デバイスにおける模擬燃料合金材料の物性評価

@王 浩キン, @佐藤 勇, @守田 幸路

日本原子力学会「2022年春の年会」  2022.3 

溶融燃料プールのスロッシング運動に伴う即発臨界挙動

@藤田 哲史, @石津 朋子, @守田 幸路

日本原子力学会「2022年春の年会」  2022.3 

FP移行挙動に着目した高速炉炉心損傷挙動解析コードASTERIA-SFRによるFAUST試験解析

@園田 大貴, @石津 朋子, @守田 幸路

日本原子力学会「2022年春の年会」  2022.3 

シビアアクシデント時の格納容器貫通部における核分裂生成物の除去効果に関する研究 (1) 実機条件を反映した格納容器貫通部FP除去試験手法の構築

@中村 康一, @金井 大造, @宇井 淳, @西村 聡, @西 義久, @劉 維, @守田 幸路

日本原子力学会「2022年春の年会」  2022.3 

Numerical Investigation on Mechanism of Heat Transfer between Molten Pool and Duct Wall in EAGLE ID1 and ID2 In-Pile Tests International conference

#Ting Zhang, @Koji Morita, @Wei Liu, @Xiaoxing Liu, @Kenji Kamiyama

The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)  2022.3 

Preliminary Application of Eutectic Reaction Model on Boron Carbide and Stainless Steel to Severe Accident Simulation of Sodium-Cooled Fast Reactors International conference

@Hidemasa Yamano, @Koji Morita

The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)  2022.3 

Flow Characteristics in Rectangular Micro-Channels with High Aspect Ratios International conference

@Wei Liu, #Kazuya Gotou, @Tsutaya Matumoto, @Koji Morita

The 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19)  2022.3 

粒子法を用いた円管内固液混合流体運動の数値シミュレー ション

#中村 武志, @守田 幸路, @劉 維, @関尾 佳弘

日本原子力学会九州支部第40回研究発表講演会  2021.12 

多孔質壁の毛細管力による液相輸送のシミュレーション

#大森 康平, ＠松元 達也, @劉 維, @守田 幸路, @岡部 弘高, @原 一広

日本原子力学会九州支部第40回研究発表講演会  2021.12 

溶融ジェットによる固体壁浸食挙動に関する3次元粒子法 シミュレーション

#高塚 大地, #中村 武志, #張 婷, @劉 維, @守田 幸路, @神山 健司

日本原子力学会九州支部第40回研究発表講演会  2021.12 

A 3D Particle-Based Analysis of Molten Pool-to-Structural Wall Heat Transfer in a Simulated Fuel Subassembly International conference

#Ting Zhang, @Koji Morita, @Xiaoxing Liu, @Wei Liu, @Kenji Kamiyama

The Second Asian Conference on Thermal Sciences (2nd ACTS)  2021.10 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (5)デバイス構造の検討と可視化試験によるデバイス内燃料移動挙動の基礎評価

@関尾 佳弘、@佐藤 勇、@川島 正俊、@守田 幸路

日本原子力学会「2021年秋の年会」  2021.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究 (25)プロジェクト全体概要及び令和２年度までの進捗

@山野 秀将、@高井 俊英、@江村 優軌、@東 英生、@福山 博之、@西 剛史、@守田 幸路、@中村 勤也、@深井 尋史、@Marco Pellegrini

日本原子力学会「2021年秋の年会」  2021.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (4)模擬燃料材料及び可溶栓材料の選択と物性評価

@佐藤 勇、#王 浩キン、#山田 大輔、@有田 裕二、#安藤 慧、#川瀬 小春、@有馬 立身、@守田 幸路

日本原子力学会「2021年秋の年会」  2021.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (3)2020年度までのプロジェクト全体進捗概要

@守田 幸路、@劉 維、@有馬 立身、@有田 裕二、@佐藤 勇、@松浦 治明、@関尾 佳弘、@相楽 洋、@川島 正俊

日本原子力学会「2021年秋の年会」  2021.9 

受動的炉停止デバイスにおける可溶栓合金材料の熱物性評価

#住吉 壮斗、@有馬 立身、@出光 一哉、@稲垣 八穂広、@守田 幸路

日本原子力学会「2021年秋の年会」  2021.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (6)デバイス効果を強化するデバイス集合体基本仕様の検討

@相楽 洋、@守⽥ 幸路、@川島 正俊、@有馬 立身、@劉 維、@有⽥ 裕⼆、@佐藤 勇

日本原子力学会「2021年秋の年会」  2021.9 

ジェット・インピンジメント挙動に関する粒子法シミュレーション

#高塚 大地、#中村 武志、#張 婷、@劉 維、@守田 幸路、@神山 健司

日本原子力学会「2021年秋の年会」  2021.9 

A 3D Numerical Simulation On Heat Transfer Behavior in EAGLE ID11 In-Pile Test Using Finite Volume Particle Method International conference

#TING ZHANG, @KOJI MORITA, @XIAOXING LIU, @WEI LIU, @KENJI KAMIYAMA

The 28th International Conference on Nuclear Engineering (ICONE 2021)  2021.8 

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019 International conference

@HIDEMASA YAMANO, @TOSHIHIDE TAKAI, @TOMOHIRO FURUKAWA, @SHIN KIKUCHI, @YUKI EMURA, @KENJI KAMIYAMA, @HIROYUKI FUKUYAMA, @HIDEO HIGASHI, @TSUYOSHI NISHI, @HIROMICHI OHTA, @KOJI MORITA, @KINYA NAKAMURA

The 28th International Conference on Nuclear Engineering (ICONE 2021)  2021.8 

A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling International conference

#MD. ADUR RAFIQ AKAND, @KOJI MORITA, @WEI LIU, @TATSUYA MATSUMOTO

The 28th International Conference on Nuclear Engineering (ICONE 2021)  2021.8 

An Improved Mechanistic Model for Prediction of Bubble Lift-off Diameter in Subcooled Flow Boiling for Inclined Heating Surface

#M. A. Rafiq Akand, #Kei Kitahara, @Tatsuya Matsumoto, @Wei Liu, @Koji Morita

日本原子力学会「2021年春の年会」  2021.3 

Particle-based simulation on heat transfer behavior between molten pool and duct wall in EAGLE ID1 and ID2 in-pile tests

#Ting Zhang, @Koji Morita, @Xiaoxing Liu, @Wei Liu, @Kenji Kamiyama

日本原子力学会「2021年春の年会」  2021.3 

強制流動サブクール沸騰の正味蒸気発生点に関する研究

#北原 渓, #M.A. Rafiq Akand， @松元 達也， @劉 維， @守田 幸路

日本原子力学会九州支部第39回研究発表講演会  2020.12 

EAGLE ID1 炉内試験における溶融プール/ダクト壁熱伝達に関する 3 次元粒子法シミュレーション

#坂口 和也, #船越 寛司, #加藤 正嗣， @劉 暁星， @劉 維， @守田 幸路， @神山 健司

日本原子力学会九州支部第39回研究発表講演会  2020.12 

Particle-Based Simulation of Jet Impingement Behaviors International conference

#D. TAKATSUKA, @K. MORITA, @W. LIU, #T. ZHANG, #T. NAKAMURA, @K. KAMIYAMA

The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12)  2022.11 

Experimental Study on Aerosol Migration Behavior in Rectangular Penetrations International conference

#M. KOGA, #K. TAKANISHI, @T. MATSUMOTO, @W. LIU, @K. MORITA, @K. NAKAMUR, @T. KANAI

The 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12)  2022.11 

A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition International conference

#M.A. RAFIQ AKAND, @T. MATSUMOTO, @W. LIU, @K. MORITA

International Topical Meeting on Advances in Thermal Hydraulics (ATH '20)  2020.10 

Bubble Lift-off Size in Subcooled Flow Boiling for Inclined Heating Surface

#Md Abdur Rafiq Akand1, #Kei Kitahara, @Tatsuya Matsumoto, @Wei Liu, @Koji Morita

日本原子力学会「2020年秋の年会」  2020.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (2) 炉心特性とデバイス応答の基本評価

@相楽 洋, @守田 幸路, @川島 正俊, @劉 維, @有田 裕二, @佐藤 勇

日本原子力学会「2020年秋の年会」  2020.9 

高速炉における炉心損傷事故の発生を防止する受動的炉停止デバイスの開発 (1)プロジェクト全体概要

@守田 幸路, @劉 維, @有馬 立身, @有田 裕二, @川瀬 小春, @佐藤 勇, @松浦 治明, @関尾 佳弘, @相楽 洋, @川島 正俊

日本原子力学会「2020年秋の年会」  2020.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究 (19) プロジェクト全体概要及び令和元年度までの進捗

@山野 秀将, @高井 俊英, @菊地 晋, @江村 優軌, @東 英生, @福山 博之, @西 剛史, @太田 弘道, @守田 幸路, @中村 勤也

日本原子力学会「2020年秋の年会」  2020.9 

気液界面で液体エントレインメントを伴う気泡膨張挙動に関する数値シミュレーション

#中村 武志, #坂口 和也, #船越 寛司, @劉 維, @守田 幸路, @神山 健司

日本原子力学会「2020年秋の年会」  2020.9 

ナトリウム冷却高速炉の炉心損傷事故時の炭化ホウ素制御棒材の共晶溶融モデルの検証

@山野 秀将, @劉 暁星, @守田 幸路

日本機械学会2020年度年次大会  2020.9 

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (4) Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide International conference

@X. LIU, @K. MORITA, @H. YAMANO

ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE  2020.8 

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2018 International conference

@H. YAMANO, @T. TAKAI, @T. FURUKAWA, @S. KIKUCHI, @Y. EMURA, @K. KAMIYAMA, @H. FUKUYAMA, @H. HIGASHI, @T. NISHI, @H. OHTA, @X. LIU, @K. MORITA

ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE  2020.8 

EAGLE ID1炉内試験における溶融プール／ダクト壁熱伝達に関する3次元粒子法シミュレーション

#坂口 和也, #船越 寛司, #加藤 正嗣, @劉 暁星, @劉 維, @守田 幸路, @神山 健司

日本原子力学会「2020年春の年会」  2020.3 

Prediction of Net Vapor Generation Point for Heating Surface with Different Inclination Angle at IVR Condition

#M. A. Rafiq Akand, @Tatsuya Matsumoto, @Wei Liu, @Koji Morita

日本原子力学会「2020年春の年会」  2020.3 

ふく射を利用した原子炉キャビティ冷却システムの伝熱特性に関する研究

#西森 友弥, #明石 知泰， #宇和田 尚悟， @松元 達也， @劉 維， @守田 幸路, @高松 邦吉

日本原子力学会九州支部第38回研究発表講演会  2019.12 

マイクロチャネルにおける流動特性に関する研究

#田中 賢太郎, #後藤 和也， @松元 達也， @劉 維， @守田 幸路

日本原子力学会九州支部第38回研究発表講演会  2019.12 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究 （18）安全解析コードで用いる共晶反応モデルの検証

@劉 暁星， @守田 幸路， @山野 秀将

日本原子力学会「2019年秋の大会」  2019.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究 (11) プロジェクト全体概要及び平成30年度までの進捗

@山野 秀将, @高井 俊秀, @古川 智弘, @菊地 晋, @江村 優軌, @神山 健司, @東 英生, @福山 博之, @西 剛史, @太田 弘道, @劉 暁星, @守田 幸路, @中村 勤也

日本原子力学会「2019年秋の大会」  2019.9 

新型炉の国際協力の現状と今後の研究開発課題（イノベーションの創出） （2）高速炉の今後の研究開発課題

@守田 幸路

日本原子力学会「2019年春の年会」  2019.3 

マイクロチャンネルにおける伝熱流動に関する実験的研究

#後藤 和也， #田中 賢太郎， #藤野 成篤， @Nugroho Tino Sawadi， @松元 達也， @劉 維， @守田 幸路

日本原子力学会「2019年春の年会」  2019.3 

溶融混合プールから構造壁への熱伝達挙動に関する３次元粒子法シミュレーション

#船越 寛司， #加藤 正嗣， @劉 暁星， @劉 維， @守田 幸路， @神山 健司

日本原子力学会「2019年春の年会」  2019.3 

高温ガス炉における受動的冷却設備の伝熱特性に関する検討

#明石 知泰， #細見 成祐， #井福 弘基， @松元 達也， @劉 維， @守田 幸路, @高松 邦吉

日本原子力学会九州支部第37回研究発表講演会  2018.12 

混合固体粒子ベッドのセルフ・レベリング挙動に関する実験的研究

#西森 友弥, #田崎 雄祐, #Phan Le Hoang Sang, @松元 達也, @劉 維, @守田 幸路

日本原子力学会九州支部第37回研究発表講演会  2018.12 

溶融炉心プールのスロッシング運動に伴うエナジェティックスに関する検討

@守田 幸路， #福田 真之， @劉 維， #帶刀 勲

日本原子力学会「2018年春の年会」  2018.3 

高温ガス炉における受動的冷却設備の伝熱特性に関する検討

#細見 成祐，　#山口 修平，　#明石 知泰, @松元 達也, @劉 維, @守田 幸路, @高松 邦吉

日本原子力学会「2018年春の年会」  2018.3 

3次元有限体積粒子法の2液相混合流動挙動解析への適用性検証

#加藤 正嗣, #小川 竜聖, #船越 寛司, @劉 暁星, @松元 達也, @劉 維, @守田 幸路, @神山 健司

日本原子力学会「2018年春の年会」  2018.3 

有限体積粒子法を用いた3次元多相流解析の検討

#船越 寛司, #加藤 正嗣, #小川 竜聖, @劉　暁星, @松元 達也, @劉　維, @守田 幸路

日本原子力学会九州支部第36回研究発表講演会  2017.12 

デブリベッドのセルフ・レベリング挙動に関する実験的研究：混合粒子ベッド高さに対する予測式の検討

#田崎 雄祐, #三浦 亮, #Phan Le Hoang Sang, @松元 達也, @劉　維, @守田 幸路

日本原子力学会九州支部第36回研究発表講演会  2017.12 

混合固体粒子の堆積挙動に関する実験的研究

#ソン エイカク, #Md Abdur Rob Sheikh, @松元 達也, @劉　維, @守田 幸路, @松場 賢一, @豊岡 淳一, @田上 浩孝, @神山 健司

日本原子力学会九州支部第36回研究発表講演会  2017.12 

デブリベッドのセルフ・レベリング挙動に関する実験的研究 :混合粒子ベッド高さに対する予測式の検討

#三浦 亮， #松岡 史也， #Ngo Phi Manh， #Phan Le Hoang Sang, @松元 達也, @劉 維, @守田 幸路

日本原子力学会「2017年秋の大会」  2017.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究（１）プロジェクト全体概要

@山野 秀将, @高井 俊秀, @古川 智弘, @江村 優軌, @倉田 正輝, @東 英生, @福山 博之, @西 剛史, @太田 弘道, @劉 暁星, @守田 幸路, @古谷 正裕

日本原子力学会「2017年秋の大会」  2017.9 

ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究 （10）安全解析コードで用いる共晶反応モデルの開発

@劉 暁星， @守田 幸路， @山野 秀将

日本原子力学会「2018年秋の大会」  2018.9 

EAGLE ID1試験における溶融燃料プールから構造壁への熱伝達機構に関する検討

@守田 幸路， #小川 竜聖， @劉 暁星， @劉 維， @神山 健司

日本原子力学会「2018年秋の大会」  2018.9 

損傷炉心プールのスロッシング挙動に関する基礎的研究　運動特性が反応度印加に与える影響（その３）

福田 真之, 渕田　翔, 松元 達也, 守田 幸路, 帶刀　勲

日本原子力学会「2017年春の年会」  2017.3 

２液相混合流動挙動に関する粒子法シミュレーションの検証

小川 竜聖, 山内 俊也, 加藤 正嗣, LIU XIAOXING, 松元 達也, 守田 幸路, 神山　健司, 鈴木　徹

日本原子力学会「2017年春の年会」  2017.3 

受動的安全性を有する原子炉圧力容器冷却設備の伝熱特性に関する研究:スケールモデルによる実験的検討

#山口 修平, #佐藤 紀恭, @松元 達也, @守田 幸路, @高松 邦吉

日本原子力学会九州支部第35回研究発表講演会  2016.12 

粒子法シミュレーションによる 2 成分混合プールの流動挙動解析

山内 俊也, 小川 竜聖, 加藤 正嗣, LIU XIAOXING, 松元 達也, 守田 幸路, 神山　健司, 鈴木　徹

日本原子力学会九州支部第35回研究発表講演会  2016.12 

損傷炉心プールにおけるスロッシング運動に伴う反応度効果についての研究

福田 真之, 渕田　翔, 帶刀　勲, 松元 達也, 守田 幸路

日本原子力学会九州支部第35回研究発表講演会  2016.12 

Sloshing of Molten Fuel Pool and the Recriticality - Reactivity insertion caused by fuel motion - Invited International conference

Koji Morita, Tatsuya Matsumoto, Isao Tatewaki, Syo Fuchita

A Topical Expert Meeting on Re-criticality Free SFR Concepts during HCDA  2016.10 

受動的安全性を持つ新しい炉容器冷却設備　(1) 実機のRCCSと比較するために等倍縮小した除熱試験装置の実験条件

高松 邦吉, 松元 達也, 守田 幸路

日本原子力学会「2016年秋の大会」  2016.9 

損傷炉心プールのスロッシング挙動に関する基礎的研究　運動特性が反応度印加に与える影響(その2)

渕田　翔, 江村 優軌, 松元 達也, 守田 幸路, 帶刀　勲

日本原子力学会「2016年秋の大会」  2016.9 

受動的安全性を持つ新しい炉容器冷却設備　(2) スケールモデルによる伝熱特性に関する実験的検討

佐藤　紀恭, 山口　修平, 松元 達也, 守田 幸路, 高松 邦吉

日本原子力学会「2016年秋の大会」  2016.9 

受動的安全性を持つ原子炉圧力容器の冷却設備：実機のRCCSと等倍縮小した除熱試験装置の比較方法

高松 邦吉, 松元 達也, 守田 幸路

日本原子力学会「2016年春の年会」  2016.3 

損傷炉心プールのスロッシング挙動に関する基礎的研究：プール運動による反応度挿入の指標に関する検討

守田 幸路, 渕田　翔, 江村 優軌, 松元 達也, 帶刀　勲

日本原子力学会「2016年春の年会」  2016.3 

デブリベッドのセルフ・レベリングに関する研究；球形・非球形混合粒子ベッドのレベリング特性

松岡 史也, 錦戸 達也, 三浦　亮, 松元 達也, 守田 幸路

日本原子力学会「2016年春の年会」  2016.3 

格子ー粒子法連成計算による混合粒子堆積挙動の数値シミュレーション

河田　凌, 大原 陽平, 藤本 拓矢, 西田 智, 守田 幸路, Liancheng Guo, 田上浩孝, 鈴木　徹

日本原子力学会「2016年春の年会」  2016.3 

大型高速炉における CMR 概念の適用による安全強化方策の考察 ー液体金属燃料デバイス概念による炉心反応度評価事例ー

川島 正俊, 原 昭浩, 坪井 靖, 守田 幸路, 遠藤 寛, 相楽 洋

日本原子力学会「2016年春の年会」  2016.3 

格子ー粒子法連成計算による固体粒子堆積挙動の数値シミュレーション

河田　凌, 大原 陽平, 藤本 拓矢, 西田 智, 守田 幸路, Liancheng Guo, 田上浩孝, 鈴木　徹

日本原子力学会九州支部第34回研究発表講演会  2015.12 

デブリベッドのセルフ・レベリングに関する研究：混合粒子ベッドのセルフ・レベリング特性

三浦　亮, 錦戸 達也, 松岡　史也, 松元 達也, 守田 幸路

日本原子力学会九州支部第34回研究発表講演会  2015.12 

燃料デブリ堆積挙動に関する実験的研究　ー混合粒子によるベッド形成挙動ー

ソン　エイカク, 神山　基紀, 森岡　徹, 守田 幸路, 松元 達也, 松場　賢一, 神山　健司, 鈴木　徹

日本原子力学会九州支部第34回研究発表講演会  2015.12 

格子ー粒子法連成計算による固体粒子堆積挙動の３次元シミュレーション

大原 陽平, 藤本 拓矢, 西田 智, 守田 幸路, Liancheng Guo, 田上浩孝, 鈴木　徹

日本原子力学会「2015年秋の大会」  2015.9 

受動的安全性を持つ新しい炉容器冷却設備

高松 邦吉, 松元 達也, 守田 幸路

日本原子力学会「2016年春の年会」  2015.9 

EAGLE ID1試験における溶融混合プールから構造壁への熱伝達挙動に関する粒子法シミュレーション

時岡　大海, 森田　亮大, 中村　吏一郎, 守田 幸路, 神山　健司, 鈴木　徹

日本原子力学会「2015年秋の大会」  2015.9 

損傷炉心プールのスロッシング挙動に関する基礎的研究：プール運動が反応度印加に与える影響

渕田　翔, 江村 優軌, 松元 達也, 守田 幸路

日本原子力学会「2015年秋の大会」  2015.9 

燃料デブリ堆積挙動に関する実験的研究　ー混合粒子によるベッド形成挙動ー

神山　基紀, 出口 亮平, 森岡　徹, 守田 幸路, 松元 達也, 松場　賢一, 神山　健司, 鈴木　徹

日本原子力学会「2015年秋の大会」  2015.9 

高速炉炉心損傷過程における固有の安全性に関する研究(4)；混合物の水流動試験結果と投入反応度挿入率の関係

帶刀 勲, 石津 朋子, 守田 幸路

日本原子力学会「2015年春の年会」  2015.3 

「第 4 世代ナトリウム冷却高速炉の安全設計ガイドラインの検討状況」　(1) 第 4 世代 Na 冷却高速炉における安全設計ガイドライン(SDG)の構築方法

守田 幸路

日本原子力学会「2015年春の年会」  2015.3 

ハイブリッド法を用いた固体粒子堆積挙動に関する数値シミュ レーション

藤本 拓矢, 西田 智, 大原 陽平, 守田 幸路, Liancheng Guo

日本原子力学会「2015年春の年会」  2015.3 

デブリベッドのセルフ・レベリングに関する研究；混合粒子ベッドのセルフ・レベリング特性

錦戸 達也, 西 津平, 松岡 史也, 松元 達也, 守田 幸路

日本原子力学会「2015年春の年会」  2015.3 

固液混相プールのスロッシング挙動に関する基礎的研究

渕田 翔, 江村 優軌, 帶刀 勲, 松元 達也, 守田 幸路, 遠藤 寛

日本原子力学会九州支部第33回研究発表講演会  2014.12 

溶融混合プールから構造壁への熱伝達機構に関する粒子法解析

中村 吏一朗, 森田 亮大, 時岡 大海, Nur Asiah Aprianti, GUO LIANCHENG, 守田 幸路

日本原子力学会九州支部第33回研究発表講演会  2014.12 

ガス吹き込みによる非球形粒子ベッドのレベリング特性に関する研究

松岡 史也, 西 津平, 錦戸 達也, 松元 達也, 守田 幸路

日本原子力学会九州支部第33回研究発表講演会  2014.12 

「部会活動としての日韓交流の 10 年と今後の活性化」　(6) 熱流動部会の日韓サマースクール/セミナー

守田 幸路

日本原子力学会「2014年秋の大会」  2014.9 

高速炉における損傷炉心プールのスロッシング挙動に関する研究：固液混合プールの運動特性

江村 優軌, 阿部 達広, 松元 達也, 守田 幸路, 帶刀 勲, 石津 朋子, 遠藤 寛

日本原子力学会「2014年秋の大会」  2014.9 

燃料デブリの堆積挙動に関する研究:非球形粒子のベッド形成特性

森岡 徹, 堀江 達郎, 神山 基紀, MD. SHAMSUZZAMAN, 松元 達也, 守田 幸路, 田上 浩孝, 鈴木 徹, 飛田 吉春

日本原子力学会「2014年秋の大会」  2014.9 

デブリベッドのセルフ・レベリングに関する研究：非球形粒子ベッドのレベリング特性

西 津平, 錦戸 達也, 竹田 祥平, 松元 達也, 守田 幸路

日本原子力学会「2014年秋の大会」  2014.9 

高速炉炉心損傷過程における固有の安全性に関する研究　(3)水流動試験結果と実機における反応度挿入率の関係

帯刀 勲, 石津 朋子, 守田 幸路

日本原子力学会「2014年秋の大会」  2014.9 

炉心損傷時の炉心物質再配置挙動評価手法の開発　(12)微視的モデルを用いたセルフ・レベリング挙動評価手法

守田 幸路, GUO LIANCHENG, ZHANG BIN, 田上 浩孝, 飛田 吉春

日本原子力学会「2014年秋の大会」  2014.9 

炉心損傷時の炉心物質再配置挙動評価手法の開発　(11) 巨視的モデルによるセルフ・レベリング挙動評価手法

田上 浩孝, 飛田 吉春, 成 松柏, GUO LIANCHENG, ZHANG BIN, 守田 幸路

日本原子力学会「2014年秋の大会」  2014.9 

炉心損傷時の炉心物質再配置挙動評価手法の開発　(7) 研究開発成果のまとめ

飛田 吉春, 鈴木 徹, 神山 健司, 松場 賢一, 磯﨑 三喜男, 田上 浩孝, 山野 秀将, 守田 幸路, ZHANG BIN, GUO LIANCHENG

日本原子力学会「2014年秋の大会」  2014.9 

受動的安全性を持つ原子炉圧力容器の冷却設備

高松 邦吉, 松元 達也, 守田 幸路

日本原子力学会「2014年秋の大会」  2014.9 

高速炉炉心損傷過程における固有の安全性に関する研究(2);水流動試験結果に基づいた遷移過程のプールスロッシングの分析

帶刀 勲, 遠藤 寛, 石津 朋子, 守田 幸路

日本原子力学会「2014年春の年会」  2014.3 

溶融混合プールから構造壁への熱伝達機構に関する粒子法解析

森田 亮大, 大島 渉, Nur Asiah Aprianti, Liancheng Guo, 守田 幸路

日本原子力学会「2014年春の年会」  2014.3 

Development of a Hybrid Particle-Mesh Method for Multiphase Flow Simulations

Liu XianXing, GUO LIANCHENG, Morita Koji

日本原子力学会「2014年春の年会」  2014.3 

3D Numerical Simulation of a Self-leveling Experiment using CFD-DEM Code

GUO LIANCHENG, Morita Koji, Tagami Hirotaka, Tobita Yoshiharu

日本原子力学会「2014年春の年会」  2014.3 

固体粒子ベッドにおけるセルフレベリング特性の定量的評価に関する研究

竹田 祥平, 西 津平, 錦戸 達也, 松元 達也, 守田 幸路

日本原子力学会九州支部第32回研究発表講演会  2013.12 

デブリベッド形成の基本特性に関する実験データベースの整備

森岡 徹, 堀江 達郎, 神山 基紀, MD. SHAMSUZZAMAN, 松元 達也, 守田 幸路, 田上 浩孝, 鈴木 徹, 飛田 吉春

日本原子力学会九州支部第32回研究発表講演会  2013.12 

高速炉における損傷炉心プールのスロッシング挙動に関する基礎的研究 ~スロッシングの増幅・緩和機構の考察~

江村 優軌, 阿部 達広, 松元 達也, 守田 幸路, 帶刀 勲, 石津 朋子, 遠藤 寛

日本原子力学会九州支部第32回研究発表講演会  2013.12 

炉心損傷時の炉心物質再配置挙動評価手法の開発;(5)巨視的モデルによるセルフ・レベリング挙動実験解析

田上 浩孝, 飛田 吉春, 成 松柏, 郭 連城, 張 斌, 守田 幸路

日本原子力学会「2013年秋の大会」  2013.9 

デブリベッド形成の基本特性に関する実験データベースの整備

堀江 達郎, 森岡 徹, MD. Shamsuzzaman, 松元 達也, 守田 幸路, 田上 浩孝, 鈴木 徹, 飛田 吉春

日本原子力学会「2013年秋の大会」  2013.9 

炉心損傷時の炉心物質再配置挙動評価手法の開発;(6) Analysis of self-leveling experiment using CFD-DEM code

Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita

日本原子力学会「2013年秋の大会」  2013.9 

高速炉の損傷炉心プールのスロッシング挙動に関する水流動試 験;スロッシングの増幅・緩和機構の考察

阿部達広, 松元 達也, 守田 幸路, 遠藤 寛, 石津 朋子, 帶刀 勲

日本原子力学会「2013秋の大会」  2013.9 

高熱流束条件下における構造壁破損挙動の粒子法シミュレーション

大島 渉, 森田 亮大, Nur Aprianti Asiah, 劉　暁星, GUO LIANCHENG, 守田 幸路

日本原子力学会「2013秋の大会」  2013.9 

Numerical Simulation of Bubbling Fluidized Bed using a CFD-DEM Hybrid Code

GUO LIANCHENG, Morita Koji, Tagami Hirotaka, Tobita Yoshiharu

日本原子力学会「2013年春の年会」  2013.3 

炉心損傷時の炉心物質再配置挙動評価手法の開発(1) 全体計画と流出挙動評価手法の開発

飛田 吉春, 神山 健司, 鈴木 徹, 松場 賢一, 田上 浩孝, 磯﨑 三喜男, 山野 秀将, 守田 幸路, GUO LIANCHENG, ZHANG BIN

日本原子力学会「2013年春の年会」  2013.3 

有限体積粒子法を用いた固気液混相流解析の モデル化手法に関する検討

荒牧 優希, 鈴木 貴人, 宮 一郎, 西田 智, GUO LIANCHENG, 守田 幸路

日本原子力学会「2013年春の年会」  2013.3 

固体粒子ベッドのセルフレベリングに関する実験データベースの構築

西 津平, 竹田 祥平, 中村 裕也, ZHANG BIN, 松元 達也, 守田 幸路, CHENG SONGBAI, 田上 浩孝, 鈴木 徹, 飛田 吉春

日本原子力学会「2013年春の年会」  2013.3 

高速炉炉心損傷過程における固有の安全性に関する研究(1) -遷移過程のプールスロッシングにおける固有の運動抑制効果-

帶刀 勲, 遠藤 寛, 石津 朋子, 守田 幸路

日本原子力学会「2013年春の年会」  2013.3 

高速炉の損傷炉心プールのスロッシング挙動に関する水流動試験:熱流動解析コードの検証

阿部 達広, 中山 慎也, 松元 達也, 守田 幸路, 帶刀 勲, 石津 朋子, 遠藤 寛

日本原子力学会「2013年春の年会」  2013.3 

デブリベッドのセルフ・レベリング挙動評価手法の開発

田上 浩孝, CHENG SONGBAI, 飛田 吉春, GUO LIANCHENG, ZHANG BIN, 守田 幸路

日本原子力学会「2013年春の年会」  2013.3 

粒子法を用いた固気液混相流解析における固相相互作用モデルの検討

宮 一郎, 鈴木貴人, 荒牧優希, 郭 連城, 守田幸路

日本原子力学会九州支部第31回研究発表講演会  2012.12 

燃料デブリの堆積挙動に関する実験的研究

堀江達郎, 森岡 徹, 浮池亮太, MD. Shamsuzzaman, 張 斌, 松元達也, 守田幸路

日本原子力学会九州支部第31回研究発表講演会  2012.12 

燃料デブリ堆積とベッド形成に関する実験的研究

浮池亮太, 堀江達郎, 森岡 徹, MD. Shamsuzzaman, 張 斌, 松元達也, 守田幸路

日本原子力学会「2012秋の大会」  2012.9 

ピン束流路における融体固化挙動の粒子法解析

武田知弥, 大島 渉, 郭 連城, 守田幸路

日本原子力学会「2012秋の大会」  2012.9 

Development of a Hybrid Method for Numerical Simulation of Multiphase Flows with Rich Solid Particles

LianCheng GUO, Koji MORITA, Yoshiharu TOBITA

日本原子力学会「2012年春の年会」  2012.3 

「第４世代ナトリウム冷却高速炉の安全設計クライテリア」特別専門委員会報告　安全設計クライテリア第1次案と論点整理

守田幸路

日本原子力学会「2012年春の年会」  2012.3 

高速炉の損傷炉心プールのスロッシング挙動に関する水流動試験:研究計画と予備検討

守田幸路, 松元達也, 中山慎也, 石津朋子, 帯刀 勲, 遠藤 寛

日本原子力学会「2012年春の年会」  2012.3 

気相吹き込みによる固体粒子ベッドのレベリング特性に関する研究

中村裕也，権代陽嗣，成 松柏，竹田祥平，張 斌，松元達也，守田幸路，山野秀将，田上浩孝，鈴木 徹，飛田吉春

日本原子力学会「2012年春の年会」  2012.3 

ガス吹き込み条件下での粒子ベッドのレベリング挙動に関する実験的研究

竹田祥平, 権代陽嗣, 中村裕也, 成 松柏, 張 斌, 松元達也, 守田幸路, 山野秀将, 田上浩孝, 鈴木 徹, 飛田吉春

日本原子力学会九州支部第30回研究発表講演会  2011.12 

固化を伴う融体―構造熱伝達の粒子―格子法による数値シミュ レーション

武田知弥, 鈴木貴人, 守田幸路, Rida Siti Nur'aini Mahmudah, 郭 連城

日本原子力学会「2011秋の大会」  2011.9 

ピン束流路での固液混合融体の侵入固化挙動に関する数値シミュレーション

中山慎也, Md.Abdul Malek Soner, 長谷川悠, 松元達也, 守田幸路, Werner Maschek

日本原子力学会「2011秋の大会」  2011.9 

デブリベッドのセルフレベリングの発達挙動に関する基礎的研究；(1) セルフレベリング挙動特性に関する実験

権代陽嗣，成 松柏，田中鷹平，甲斐貴之，張　斌，松元達也，守田幸路，山野秀将，鈴木徹，飛田吉春

日本原子力学会「2011年春の年会」  2011.3 

デブリベッドのセルフレベリングの発達挙動に関する基礎的研究；(2) Investigation of Empirical Model for Self-Leveling Development

S. Cheng, Y. Gondai, Y. Tanaka, T. Kai, B. Zhang, T. Matsumoto, K. Morita, T. Suzuki, H. Yamano, Y. Tobita

日本原子力学会「2011年春の年会」  2011.3 

原子炉の安全性 Invited

守田幸路

第9回日本予防医学リスクマネージメント学会学術総会  2011.3 

デブリベッドのセルフレベリングの発達挙動に関する研究

甲斐貴之, 田中鷹平, 権代陽嗣, 中村裕也, 浮池亮太, Songbai Cheng, Bin Zhang, 松元達也, 守田幸路, 山野秀将, 鈴木徹, 飛田吉春

日本原子力学会九州支部第29回研究発表講演会  2010.12 

格子-粒子法による構造-融体熱伝達解析手法の開発

隈部正洋, Rida Siti Nuraini Mahmudah, 鈴木貴人, 武田知弥, 郭 連城, 守田幸路, 福田研二

日本原子力学会九州支部第29回研究発表講演会  2010.12 

粒子ベッド内の固気液3相流動様式に関する基礎的研究

権代陽嗣, 田中鷹平, Songbai Cheng, Bin Zhang, 松元達也, 守田幸路, 福田研二, 山野秀将, 鈴木徹, 飛田吉春

日本原子力学会九州支部第29回研究発表講演会  2010.12 

デブリベッド内の固気液3相流動に関する基礎的研究

田中鷹平, 権代陽嗣, 成　松柏, 松元達也, 守田幸路, 福田研二, 山野秀将, 鈴木　徹, 飛田吉春

日本原子力学会「2010秋の大会」  2010.9 

新技術を活用した高速炉の次世代安全解析手法に関する研究開発；(40) COMPASS コードの熱流体力学部の検証

山本雄一, 大上雅哉, 平野悦丈, 清水泉介, 白川典幸, 越塚誠一, 守田幸路

日本原子力学会「2010秋の大会」  2010.9 

新技術を活用した高速炉の次世代安全解析手法に関する研究開発；(42)金属燃料の共晶研究 (a) 金属燃料の共晶反応に及ぼすマイナーアクチニドの効果とB4C-Fe 系状態図の評価

有馬立身, 守田幸路

日本原子力学会「2010秋の大会」  2010.9 

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

守田幸路, 山野秀将, 飛田吉春

日本原子力学会「2010秋の大会」  2010.9 

固体粒子を伴う溶融金属のピン束流路内における固化・閉塞挙動に関する研究

長谷川 悠, Sonar Md. Abdul Malek, 日室佑介, 瀬尾俊一, 松元達也, 守田幸路, 福田研二, Werner Maschek

日本原子力学会「2010秋の大会」  2010.9 

Multi-component, Multi-phaseFlow Simulationsfor Fast Reactor Safety Analysis Invited International conference

Koji Morita

CFD workshop, The 18th International Conference on Nuclear Engineering (ICONE-18)  2010.5 

Numerical Simulation of 3D Particulate Sloshing flow Using FVP/DEM Method

LianCheng GUO, Shuai ZHANG,　Koji MORITA, Kenji FUKUDA

日本原子力学会「2010年春の年会」  2010.3 

Molten Metal Freezing Simulation using Finite Volume Particle Method

Rida SN MAHMUDAH, Masahiro KUMABE, Takahito SUZUKI, LianCheng GUO, Koji MORITA, Kenji FUKUDA

日本原子力学会「2010年春の年会」  2010.3 

高速炉の炉心損傷評価技術(レベル2PSA)の開発；(12)研究開発の総括

中井良大, 鈴木 徹, 神山健司, 小山和也, 守田幸路

日本原子力学会「2010年春の年会」  2010.3 

固体粒子を混合した溶融金属の侵入固化挙動に関する研究

瀬尾俊一, Md. Abdul Malek Soner, 日室佑介, 長谷川悠, 松元達也, 守田幸路, 福田研二

日本原子力学会九州支部第28回研究発表講演会  2009.12 

有限体積粒子法による多成分多相流解析手法の開発

鈴木貴人, 郭 連城, Rida SITI NUR'AINI MAHMUDAH, 隈部正洋, 古庄千紘, 松元達也, 守田幸路, 福田研二

日本原子力学会九州支部第28回研究発表講演会  2009.12 

ピン束流路における溶融金属の侵入固化挙動に関する実験的研究

日室 佑介, コビール ホッセイン, 松元 達也, 守田 幸路, 福田 研二, Werner Maschek

日本原子力学会「2009秋の大会」  2009.9 

新技術を活用した高速炉の次世代安全解析手法に関する研究開発；(34) 金属燃料の共晶研究 (a)U-Pu-Zr-Fe 系状態図の評価と共晶反応の電子状態解析

有馬 立身, 守田 幸路

日本原子力学会「2009秋の大会」  2009.9