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List of Papers
Koji Morita Last modified date：2024.04.17

Professor / Nuclear Energy Systems / Department of Applied Quantum Physics and Nuclear Engineering / Faculty of Engineering


Papers
1. M.I. HOSAN, K. TAKANISHI, K. MORITA, W. LIU, X. CHENG, Investigations on aerosol transport and deposition behavior during severe reactor accident, Mechanical Engineering Journal, 11, 2, 23-00423, 2024.03.
2. 川島 正俊, 相楽 洋, 守田 幸路, 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－, 第44回日本核物質管理学会年次大会論文集, #4412, 2023.11.
3. H. YAMANO, K. MORITA, Preliminary Analysis of Severe Accident in Sodium-Cooled Fast Reactor Using Eutectic Reaction Model of Boron-Carbide Control-Rod Material, Proc. of 20th International Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), 41341, 2023.08.
4. K. MORITA, W. LIU, T. ARIMA, Y. ARITA, I. SATO, Y. SEKIO, H. SAGARA, M. KAWASHIMA, 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, Proc. of 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1582, 2023.05.
5. H. SAGARA, M. KAWASHIMA, K. MORITA, W. LIU, T. ARIMA, Y. ARITA, I. SATO, Y. SEKIO, 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, Proc. of 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1811, 2023.05.
6. M.I. HOSAN, M. KOGA, A. KAKOI, K. MORITA, W. LIU, X. CHENG, Experimental Study on Accident Source Terms Transport and Deposition Behavior in Nuclear Power Plants, Proc. of 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1806, 2023.05.
7. T. ZHANG, Y. YAO, K. MORITA, X. LIU, W. LIU, Y. IMAIZUMI, K. KAMIYAMA, A Large-Scale Particle-Based Simulation of Heat And Mass Transfer Behavior in EAGLE ID1 In-Pile Test, Proc. of 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1806, 2023.05.
8. Z. ZOU, K. MORITA, W. LIU, Development of a Simplified One-Dimensional CDA Bubble Model for Source Term Evaluation, Proc. of 30th International Conference on Nuclear Engineering (ICONE30), ICONE30-1048, 2023.05.
9. K. MORITA, W. LIU, T. ARIMA, Y. ARITA, I. SATO, Y. SEKIO, H. SAGARA, M. KAWASHIMA, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study, Journal of Nuclear Engineering and Radiation Science, 10.1115/1.4056834, 9, 2, 021301, 2023.03.
10. K. MORITA, W. LIU, T. ARIMA, Y. ARITA, I. SATO, Y. SEKIO, H. SAGARA, M. KAWASHIMA, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications, Journal of Nuclear Engineering and Radiation Science, 10.1115/1.4056854, 9, 4, 041302, 2023.03.
11. R.S. MAHMUDAH, K. MORITA, Eulerian vs Lagrangian Method for Low Computational Resources: A Comparison of 2D Dam Break Case, Trend in Science, 20, 6, 5539, 2023.03.
12. 川島 正俊, 相楽 洋, 守田 幸路, 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, 第43回日本核物質管理学会年次大会論文集, #4304, 2022.11.
13. M. KOGA, K. TAKANISHI, T. MATSUMOTO, W. LIU, K. MORITA, K. NAKAMUR, T. KANAI, Experimental Study on Aerosol Migration Behavior in Rectangular Penetrations, Proc. of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12), N12P1042, 2022.10.
14. D. TAKATSUKA, K. MORITA, W. LIU, T. ZHANG, T. NAKAMURA, K. KAMIYAMA, Particle-Based Simulation of Jet Impingement Behaviors, Proc. of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12), N12P1046, 2022.10.
15. T. ZHANG, K. MORITA, X. LIU, W. LIU, K. KAMIYAMA, A 3D Particle-Based Simulation of Heat and Mass Transfer Behavior in the EAGLE ID1 In-Pile Test, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2022.109389, 179, 2022.08.
16. K. MORITA, W. LIU, T. ARIMA, Y. ARITA, I. SATO, Y. SEKIO, H. SAGARA, M. KAWASHIMA, Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Basic Device, Proc. of 2022 29th International Conference on Nuclear Engineering (ICONE29), ICONE29-91812, 2022.08.
17. T. ZHANG, K. MORITA, W. LIU, X. LIU, K. KAMIYAMA, Numerical Investigation on Mechanism of Heat Transfer between Molten Pool and Duct Wall in EAGLE ID1 and ID2 In-Pile Tests, Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 33908, 2022.03.
18. W. LIU, K. GOTOU, T. MATSUMOTO, K. MORITA, Flow Characteristics in Rectangular Micro-Channels with High Aspect Ratios, Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 35877, 2022.03.
19. H. YAMANO, K. MORITA, Preliminary Application of Eutectic Reaction Model on Boron Carbide and Stainless Steel to Severe Accident Simulation of Sodium-Cooled Fast Reactors, Proc. of 19th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), 34961, 2022.03.
20. M.A. RAFIQ AKAND, W. LIU, T. MATSUMOTO, K. MORITA, Mechanistic Critical Heat Flux Prediction for In-Vessel Retention Conditions, Nuclear Engineering and Design, https://doi.org/10.1016/j.nucengdes.2021.111494, 58, 384, 2021.12.
21. M.A. RAFIQ AKAND, K. KITAHARA, T. MATSUMOTO, W. LIU, K. MORITA, Experimental Study and Modeling of Bubble Lift-Off Diameter in Subcooled Flow Boiling Including the Inclination Effect of the Heating Surface, Journal of Nuclear Science and Technology, 58, 11, 1195-1209, 2021.11.
22. K. TAKAMATSU, T. MATSUMOTO, W. LIU, K. MORITA, 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, Annals of Nuclear Energy, https://doi.org/10.1016/j.anucene.2021.108512, 162, 2021.11.
23. TING ZHANG, KOJI MORITA, XIAOXING LIU, WEI LIU, KENJI KAMIYAMA, A 3D Numerical Simulation On Heat Transfer Behavior in EAGLE ID1 In-Pile Test Using Finite Volume Particle Method, Proc. of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE2021-61469, 2021.08.
24. MD. ADUR RAFIQ AKAND, KOJI MORITA, WEI LIU, TATSUYA MATSUMOTO, A Modified Model for the Net Vapor Generation Point and Its Application on CHF Prediction in Subcooled Flow Boiling, Proc. of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE2021-64022, 2021.08.
25. HIDEMASA YAMANO, TOSHIHIDE TAKAI, TOMOHIRO FURUKAWA, SHIN KIKUCHI, YUKI EMURA, KENJI KAMIYAMA, HIROYUKI FUKUYAMA, HIDEO HIGASHI, TSUYOSHI NISHI, HIROMICHI OHTA, KOJI MORITA, KINYA NAKAMURA, 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, Proc. of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE2021-63301, 2021.08.
26. K. MORITA, W. LIU, T. ARIMA, Y. ARITA, K. KAWASE, I. SATO, H. MATSUURA, Y. SEKIO, M. KAWASHIMA, Development of a Passive Reactor Shutdown Device for Prevention of Core Disruptive Accidents in Fast Reactors: Project Overview and Preliminary Results, Proc. of the 28th International Conference on Nuclear Engineering (ICONE28), ICONE28-64099, 2021.08.
27. X. LIU, K. MORITA, S. ZHANG, Machine‐learning‐based surface tension model for multiphase flow simulation using particle method, International Journal for Numerical Methods in Fluids, 10.1002/fld.4886, 93, 2, 356-368, 2021.02.
28. K. TAKAMATSU, T. MATSUMOTO, W. LIU, K. MORITA, Comparison between Passive Reactor Cavity Cooling Systems Based on Atmospheric Radiation and Atmospheric Natural Circulation, Annals of Nuclear Energy, 10.1016/j.anucene.2020.107867, 151, 2021.02.
29. T. ZHANG, K. FUNAKOSHI, X. LIU, W. LIU, K. MORITA, K. KAMIYAMA, Numerical Simulation of Heat Transfer Behavior in EAGLE ID1 In-Pile Test Using Finite Volume Particle Method, Annals of Nuclear Energy, 10.1016/j.anucene.2020.107856, 150, 2021.01.
30. X. LIU, K. MORITA, S. ZHANG, Direct Numerical Simulation of Incompressible Multiphase Flow with Vaporization Using Moving Particle Semi-implicit Method, Journal Computational Physics, https://doi.org/10.1016/j.jcp.2020.109911, 425, 2021.01.
31. M.A. RAFIQ AKAND, T. MATSUMOTO, W. LIU, K. MORITA, A Modified Liquid Sublayer Dryout Model for Subcooled Flow Boiling Critical Heat Flux Prediction in IVR Condition, International Topical Meeting on Advances in Thermal Hydraulics (ATH '20), 1074-1087, 2020.10.
32. MD A.R. SHEIKH, X. LIU, T. MATSUMOTO, K. MORITA, L. GUO, T. SUZUKI, K. KAMIYAMA, Numerical Simulation of the Solid Particle Sedimentation and Bed Formation Behaviors Using a Hybrid Method, Energies, 10.3390/en13195018, 13, 19, 5018, 2020.09.
33. H. YAMANO, T. TAKAI, T. FURUKAWA, S. KIKUCHI, Y. EMURA, K. KAMIYAMA, H. FUKUYAMA, H. HIGASHI, T. NISHI, H. OHTA, X. LIU, K. MORITA, 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, Proc. of ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE, ICONE28-POWER2020-16102, 2020.08.
34. X. LIU, K. MORITA, H. YAMANO, 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, Proc. of ASME's POWER2020 and Nuclear Engineering Conference powered by ICONE, ICONE28-POWER2020-16175, 2020.08.
35. X. LIU, K. MORITA, S. ZHANG, Comparative study of Two Corrective Gradient Models in the Simulation of Multiphase Flows Using Moving Particle Semi-Implicit Method, International Journal for Numerical Methods in Fluids, 10.1002/fld.4796, 92, 6, 573-586, 2020.06.
36. Xiaoxing Liu, Koji Morita, Shuai Zhang, A stable moving particle semi-implicit method with renormalized Laplacian model improved for incompressible free-surface flows, Computer Methods in Applied Mechanics and Engineering, 10.1016/j.cma.2019.07.019, 356, 199-219, 2019.11, We present a stable and accurate moving particle semi-implicit (MPS) for free-surface flows. For simulating free-surface flows, previous formulations using renormalized procedure is only applicable to interior particles. Poor accuracy of the free-surface particle in turn contaminate the overall solution accuracy. In this study, dummy particle is introduced to stabilize the renormalized Laplacian model on free surface and to enforce the free-surface condition. The proposed renormalized Laplacian model enables accurate pressure calculation for both internal and free-surface particles. Modification also includes a modified gradient model in which linear consistency is guaranteed and stability is enhanced by introducing dummy particle. The proposed MPS scheme provides a more accurate and stable simulation of incompressible free surface flows. Several two-dimensional numerical simulations are presented to demonstrate the enhanced performance of the proposed MPS method..
37. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, Comparative methodology between actual RCCS and downscaled heat-removal test facility, Annals of Nuclear Energy, 10.1016/j.anucene.2019.07.025, 133, 830-836, 2019.11, Previously, a reactor cavity cooling system (RCCS) has been reported with passive safety features comprising of two continuous closed regions, namely an ex-reactor pressure vessel region and cooling region with a heat-transfer surface to ambient air. The novel shape of the RCCS allows it to efficiently remove heat released from the reactor pressure vessel (RPV) via thermal radiation and natural convection. The RCCS design significantly reduces the possibility of losing the heat sink for decay heat-removal during nuclear accidents including a station blackout by employing air as a working fluid and ambient air as ultimate heat sink. RCCS has the potential to stably and passively remove heat released from the RPV and decay heat following a reactor shutdown. The RCCS achieved a heat-removal rate of approximately 3 kW/m2. On the contrary, the heat fluxes from the RPV surface of the high temperature engineering test reactor and commercial high temperature gas-cooled reactors are 1.23–2.46 kW/m2 and approximately 3.0 kW/m2, respectively. In the previous report, the authors changed the adiabatic boundary conditions and considered the heat dissipation effect from the RPV region to ground through the RCCS wall via heat conduction; therefore, the authors could improve the system's heat-removal capability to increase its thermal reactor power level. Moreover, considering the possibilities for doubling the heat-transfer areas and increasing the emissivities, heat flux removed by the RCCS could potentially reach 7.0 kW/m2. Herein, the authors conduct a comparative methodology between an actual RCCS and a downscaled heat-removal test facility..
38. Xiaoxing Liu, Koji Morita, Shuai Zhang, A conservative finite volume-particle hybrid method for simulation of incompressible interfacial flow, Computer Methods in Applied Mechanics and Engineering, 10.1016/j.cma.2019.06.035, 355, 840-859, 2019.10, Coupling the finite volume method (FVM) and the moving-particle semi-implicit (MPS) method, a conservative hybrid method is proposed for simulation of incompressible interfacial flow. In this hybrid method, bulk flow is resolved using the multi-moment constrained interpolation profile (CIP) FVM while the interface region is rendered using moving particles calculated by several enhanced MPS schemes. A new boundary condition is developed for particles located on the boundary of the interface. Numerical particles in the MPS method are used to determine the density of each mesh cell and the conservation of mass is guaranteed by a volume-fraction remedy procedure. The approach allows accurate interface tracking without diminishing numerical efficiency. Several benchmark simulations are conducted to demonstrate the accuracy and efficiency of the proposed hybrid method..
39. 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, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project overview, Proc. of International Nuclear Fuel Cycle Conference (Global 2019), 418-427, 2019.09.
40. X.LIU, K. MORITA, H. YAMANO, 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, Proc. of International Nuclear Fuel Cycle Conference (Global 2019), 47-51, 2019.09.
41. Xiaoxing Liu, Koji Morita, Shuai Zhang, An ALE pairwise-relaxing meshless method for compressible flows, Journal of Computational Physics, 10.1016/j.jcp.2019.02.037, 387, 1-13, 2019.06, In this paper, we present a pairwise-relaxing meshless (PRM) method for solving the Euler equations of compressible flows within the Arbitrary Lagrangian Eulerian (ALE) framework. Derived from the moving particle semi-implicit (MPS) method and the finite volume particle (FVP) method, the PRM approximates the derivatives from the value defined at the midpoint of each interacting particle pairs through a kernel-based formulation. Pairwise-relaxing constants are introduced to the kernels to provide degree of freedom to enforce the Taylor-series consistency condition while mass, momentum and energy are conserved exactly. An upwind high-order reconstruction scheme via a corrective procedure and variable cut-off radius is also developed for this PRM method. The HLLC approximate Riemann solver is adopted to solve Riemann problem. One and two-dimensional numerical tests are presented to demonstrate the performance of the PRM method..
42. Xiaoxing Liu, Koji Morita, Shuai Zhang, A pairwise-relaxing incompressible smoothed particle hydrodynamics scheme, Computer Methods in Applied Mechanics and Engineering, 10.1016/j.cma.2019.01.029, 348, 297-312, 2019.05, We present a formulation of incompressible smoothed particle hydrodynamics (ISPH) method that utilizes pairwise-relaxing kernel to achieve approximately first-order consistency. Previous high-order formulations by using reproduced and corrected kernel function have had difficulties in ensuring momentum conservation. In the new scheme, relaxing constants for each kernel function are determined pair-wisely throughout the entire calculation domain by enforcing the Taylor-series consistency condition. We call this modified ISPH method Pairwise-Relaxing ISPH, or PR-ISPH. PR-ISPH retains high-order accuracy for non-uniform particle distributions. The spatial symmetry of the kernel function is kept in PR-ISPH thus momentum is strictly conserved. Several two-dimensional benchmark calculations are conducted to demonstrate the accuracy as well as the conservation property of the PR-ISPH..
43. Le Hoang Sang Phan, Phi Manh Ngo, Ryo Miura, Yusuke Tasaki, Tatsuya Matsumoto, Wei Liu, Koji Morita, Self-leveling behavior of mixed solid particles in cylindrical bed using gas-injection method, Journal of nuclear science and technology, 10.1080/00223131.2018.1531077, 56, 1, 111-122, 2019.01, The self-leveling of debris beds is a critical phenomenon to be clarified in the safety assessment of material relocation and decay heat-removal phases in postulated core-disruptive accidents in sodium-cooled fast reactors. In recent years, we have conducted several series of experiments using simulant materials to develop an experimental database of self-leveling processes in particle beds and proposed an empirical model to predict the bed height during self-leveling. The obtained experimental knowledge and proposed model applicability have been limited to homogeneous particles, although fragmented core debris could be mainly mixtures of fuel and stainless-steel particles with a size distribution. We conducted self-leveling experiments using mixtures of solid particles with different properties to understand the characteristics of self-leveling phenomena under a wider range of conditions. An improved empirical model for transient bed height was developed to correlate the experimental data under various conditions of particle mixtures. The developed model reproduces the self-leveling development of mixed particle beds and those of the homogeneous particle reasonably..
44. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Wei Liu, Koji Morita, 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, Annals of Nuclear Energy, 10.1016/j.anucene.2018.08.047, 122, 201-206, 2018.12, A previously-reported concept of reactor cavity cooling system (RCCS) with passive safety features consists of two continuous closed regions: an ex-reactor pressure vessel region and a cooling region with a heat-transfer surface to ambient air. The RCCS uses a novel shape to efficiently remove the heat released from the reactor pressure vessel (RPV) through thermal radiation and natural convection. Employing air as a working fluid and ambient air as an ultimate heat sink, the novel RCCS design strongly reduces the possibility of losing the heat sink for decay-heat-removal during nuclear accidents including a station blackout. The RCCS could stably and passively remove the heat released from the RPV and the decay heat after reactor shutdown. The previously-reported heat-removal rate of the RCCS was approximately 3 (kW/m2). The heat flux from the RPV surface of the High Temperature engineering Test Reactor (HTTR) is almost in the same range; 1.23–2.46 (kW/m2). In this paper, the authors address an improvement of heat-removal capability by considering potential of heat leakage due to heat conduction through the RCCS wall aimed at increasing a thermal reactor power level. Under the assumption of doubling the RCCS wall heat transfer area, a heat-flux removed by the RCCS could be doubled, such as approximately 6.2 (kW/m2)..
45. M. KATO, K. FUNAKOSHI, X. LIU, T. MATSUMOTO, W. LIU, K. MORITA, K. KAMIYAMA, Validation of Three-Dimensional Finite-Volume-Particle Method for Simulation of Liquid-Liquid Mixing Flow Behavior, Proc. of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11), N11P0033, 2018.11.
46. S. HOSOMI, T. AKASHI, T. MATSUMOTO, W. LIU, K. MORITA, K. TAKAMATSU, Experimental Study on Heat Removal Performance of A New Reactor Cavity Cooling System (RCCS), Proc. of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS11), N11P0045, 2018.11.
47. K. MORITA, R. OGAWA, H. TOKIOKA, X. LIU, W. LIU, K. KAMIYAMA, Particle-based Simulation of Heat Transfer Behavior in EAGLE ID1 In-Pile Test, Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Paper No. 683, 2018.10.
48. X. LIU, K. MORITA, H. YAMANO, Modeling of Eutectic Reaction Between Molten Stainless Steel and B4C for Severe Accident Simulations, Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Paper No. 572, 2018.10.
49. L.H.S. PHAN, Y. OHARA, R. KAWATA, X. LIU, W. LIU, K. MORITA, L. GUO, K. KAMIYAMA, H. TAGAMI, Numerical Simulation on Self-leveling Behavior of Mixed Particle Beds Using Multi-fluid Model Coupled with DEM, Proc. of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12), Paper No. 737, 2018.10.
50. Xiaoxing Liu, Ryusei Ogawa, Masatsugu Kato, Koji Morita, Shuai Zhang, Accuracy and stability enhancements in the incompressible finite-volume-particle method for multiphase flow simulations, Computer Physics Communications, 10.1016/j.cpc.2018.04.020, 230, 59-69, 2018.09, For the simulation of multiphase flows, an incompressible finite volume particle (IFVP) method is proposed that offers enhanced accuracy and stability. A high-order multiphase Laplacian operator is derived by combining the gradient model and divergence model. To produce enhanced accuracy, neighboring dummy particle is introduced in each dimension of the calculation and used for the discretization of the gradient model. The error-compensating terms produced by introducing these dummy particles assist in the higher-order calculations of the gradient operator. Consequently, accuracy of the Laplacian operator is enhanced consistently by these error-compensating terms. Compared to the single dummy particle introduced for two-dimensional calculations in our previous work (Liu et al., 0000), the proposed high-order scheme is more generalized and can be applied in the calculation of arbitrary dimensions. This enhanced multiphase scheme provides accurate and stable calculations of multiphase flows characterized by high density ratios. An advantage of this scheme is that the separation of two liquids of similar density is easily handled as well. Results of several numerical simulations are given to demonstrate its validity and enhanced performance..
51. Xiaoxing Liu, Koji Morita, Shuai Zhang, An advanced moving particle semi-implicit method for accurate and stable simulation of incompressible flows, Computer Methods in Applied Mechanics and Engineering, 10.1016/j.cma.2018.05.005, 339, 467-487, 2018.09, An advanced moving particle semi-implicit (MPS) method for the simulation of incompressible flows that provides enhanced accuracy and stability is proposed. Up to now, existing high-order accurate MPS pressure gradient schemes suffer from instability produced by attractive pressure gradient while some stabilized pressure gradient schemes have the shortcomings of large discretization error. We propose a high-order stabilized gradient model in which first-order Taylor-series consistency is ensured and stability is guaranteed by purely repulsive pressure gradient. Laplacian model and divergence model are modified and enable accurate and stable solution for the pressure Poisson equation (PPE). The proposed MPS scheme provides a more accurate and stable simulation of incompressible flows. Several two-dimensional numerical simulations are presented to demonstrate the enhanced performance of the proposed MPS method..
52. Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Kenichi Matsuba, Kenji Kamiyama, Tohru Suzuki, Sedimentation behavior of mixed solid particles, journal of nuclear science and technology, 10.1080/00223131.2017.1419888, 55, 6, 623-633, 2018.06, During the material relocation phase of core-disruptive accidents in sodium-cooled fast reactors, the sedimentation behavior of fragmented debris discharged from the reactor core into the lower plenum region leading to a debris-bed formation is crucial in regard to in-vessel retention and safety concerns. The height of the beds formed may influence both the cooling of the bed from the decay heat in the fuel and the neutronic characteristics. To develop an experimental database of bed formation behavior, a series of experiments using simulant materials, namely, Al2O3, ZrO2, and stainless steel, were performed under gravity-driven discharge of solid particles from a nozzle into a quiescent cylindrical water pool. The bed height was measured for particles of different size, density, and sphericity, and an injection nozzle with varying diameter, injection velocity, and injection height. From these experiments, an empirical correlation was established to predict the bed height for both homogeneous and mixed particles for the different properties. This correlation reproduces reasonably well the experimental trend in bed height with critical factors, which were identified in this and previous experiments..
53. Hirotaka Tagami, Songbai Cheng, Yoshiharu Tobita, Koji Morita, Model for particle behavior in debris bed, Nuclear Engineering and Design, 10.1016/j.nucengdes.2017.12.029, 328, 95-106, 2018.03, In analyzing the safety of core disruptive accidents in Sodium-cooled Fast Reactors (SFRs), it is important to evaluate whether the decay heat of debris bed can be removed. The decay heat removability changes depending on the shape of debris bed, which would be deformed by coolant vapor with time. In the present paper, a new model was developed to analyze debris bed behavior with SIMMER, which is a safety analysis code for SFRs. In the new model, the effects of inter-particle collisions and contacts are modeled as inter-particle interaction. Test simulation results show the roles of physical properties in the new model on the dense particle behavior. Assessment results of proposed model based on model experiments indicate that the new model is capable of describing the transient of the shape of the particle bed in the liquid driven by the gas phase. Considering the fact that the process of leveling behavior in model experiments is common for the debris bed in SFRs, the new model can be employed as an analysis tool for debris bed behavior..
54. M. Shamsuzzaman, T. Horie, F. Fuke, M. Kamiyama, T. Morioka, Tatsuya Matsumoto, Koji Morita, H. Tagami, T. Suzuki, Y. Tobita, Experimental study on debris bed characteristics for the sedimentation behavior of solid particles used as simulant debris, Annals of Nuclear Energy, 10.1016/j.anucene.2017.09.011, 111, 474-486, 2018.01, Particle bed characteristics are experimentally investigated for the sedimentation and subsequent bed formation of solid particles, related to the coolability aspects in core–disruptive accidents. Presently a series of experiments with gravity driven discharge of solid particles into a quiescent water pool was performed to evaluate bed formation characteristic in the course of particle sedimentation. We evaluated the effects of the crucial factors: nozzle diameter, particle density, particle diameter and nozzle height on four key quantitative parameters of bed shape: mound dimple area, mound dimple volume, repose angle and mound height to illustrate the role of the crucial factors on forming the particle bed shape. The investigated crucial factors exhibit a significant role that diversifies the particle bed formation process. Based on the data obtained in the experimental observations, we developed an empirical correlation to compare the predicted results with the experimental bed heights. The proposed empirical correlation can reasonably demonstrate the general trend of the experimental bed height. This correlation could be useful to assess the particle bed elevation, and to identify the governing parameters..
55. Werner Maschek, Rui Li, Claudia Matzerath Boccaccini, Fabrizio Gabrielli, Koji Morita, Investigation on upper bounds of recriticality energetics of hypothetical core disruptive accidents in sodium cooled fast reactors, Nuclear Engineering and Design, 10.1016/j.nucengdes.2017.11.002, 326, 392-402, 2018.01, One key research goal for GEN-IV systems is an enhanced safety compared to the former Sodium Cooled Fast Reactor concepts. A key issue is built-in safety and the capability to prevent accidents and to demonstrate that their consequences do not violate aimed-at safety criteria. From the beginning of SFR development the Core Disruptive Accident (CDA) has played an outstanding role in the safety assessment. Under core disruptive accident conditions with core melting the fuel might compact, prompt criticality might be achieved and a severe nuclear power excursion with mechanical energy release might be the consequence. Numerous safety analyses accompanied the development and the licensing procedures of past fast reactor projects. A central issue of all analyses was the assessment of a realistic upper bound of energetics especially related to recriticalities in disrupted core configurations. Striving for an even higher safety level for next generation reactors a new strategy focused on the development and introduction of preventive and mitigative measures both to reduce the chance for a severe accident development and to mitigate its energetics. For assessing the effectiveness of these measures the knowledge of the CDA behavior is essential. In this context and on basis of new code developments, new experimental insights and extended studies for many reactor types of different power classes over the recent years, the issue of a realistic upper bound of energetics of the late core melt phases is again of relevance. Of special interest is the identification of natural and intrinsic mechanisms that limit the escalation of energetics. The current paper deals with these issues and tries to add supportive facts on the limits of CDA energetics. The evaluation of results of mechanistic SIMMER-II and SIMMER-III/IV analyses performed for various core designs and power classes and specific model case studies in 2D and 3D geometry indeed supports the idea of a limit of recriticality energetics. Intrinsic mechanisms exist, which limit the escalation energetics even in case of a strong blockage confinement suppressing any fuel discharge and allowing on-going sloshing recriticalities. In the light of the available information and taking into account relevant scientific publications and studies by the international community on the subject, one could conclude that an upper bound for energetics in the range given in the paper can be deduced..
56. X. Liu, K. Morita, S. Zhang, Enhancement of the accuracy of the finite volume particle method for the simulation of incompressible flows, International Journal for Numerical Methods in Fluids, 10.1002/fld.4404, 85, 12, 712-726, 2017.12, A finite volume particle (FVP) method for simulation of incompressible flows that provides enhanced accuracy is proposed. In this enhanced FVP method, a dummy neighbor particle is introduced for each particle in the calculation and used for the discretization of the gradient model and Laplacian model. The error-compensating term produced by introducing the dummy neighbor particle enables higher order terms to be calculated. The proposed gradient model and Laplacian model are applied in both pressure and pressure gradient calculations. This enhanced FVP scheme provides more accurate simulations of incompressible flows. Several 2-dimensional numerical simulations are given to confirm its enhanced performance..
57. L.H.S. PHAN, P.M. NGO, F. MATSUOKA, R. MIURA, T. MATSUMOTO, K. MORITA, Experimental Study on Self-Leveling Behavior of Binary-Mixed Particles in Cylindrical Bed Using Gas-Injection Method, Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Paper No. 20828, 2017.09.
58. R. KAWATA, Y. OHARA, M.A.R. SHEIKH, X. LIU, T. MATSUMOTO, K. MORITA, L. GUO, K. KAMIYAMA, T. SUZUKI, Numerical Simulation of Solid-Particle Sedimentation Behavior Using a Multi-Fluid Model Coupled with DEM, Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Paper No. 21462, 2017.09.
59. 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 , IAEA's Coordinated Research Project on EBR-II Shutdown Heat Removal Tests, Proc. of 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-17), Paper No. 21729, 2017.09.
60. 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, EBR-II Passive Safety Demonstration Tests Benchmark Analyses, Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-4, 2017.06.
61. S. KUBO, K. MORITA, K. KAMIYAMA, T. SUZUKI, The Status of Safety Research in the Field of Sodium-Cooled Fast Reactors in Japan, Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-28, 2017.06.
62. B. VEZZONI, M. MARCHETTI, L. ANDRIOLO,F. GABRIELLI, X. CHEN, C. MATZERATH BOCCACCINI, A. RINEISKI, W. MASCHEK, K. MORITA, T. ARIMA, SIMMER Analyses of the EBR-II Shutdown Heat Removal Tests, Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-72, 2017.06.
63. 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, Final Results and Lessons Learned From EBR-II SHRT-17 Benchmark Simulations, Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-84, 2017.06.
64. 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, IAEA's Coordinated Research Project on EBR-II Shutdown Heat Removal Tests: An Overview, Proc. of International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development, IAEA-CN245-361, 2017.06.
65. Liancheng Guo, Koji Morita, Yoshiharu Tobita, Numerical simulations on self-leveling behaviors with cylindrical debris bed, Nuclear Engineering and Design, 10.1016/j.nucengdes.2017.02.024, 315, 61-68, 2017.04, The postulated core disruptive accidents (CDAs) are regarded as particular difficulties in the safety analysis of liquid-metal fast reactors (LMFRs). In the CDAs, core debris may settle on the core-support structure and form conic bed mounds. Then debris bed can be levelled by the heat convection and vaporization of surrounding coolant sodium, which is named “self-leveling behavior”. The self-leveling behavior is a crucial issue in the safety analysis, due to its significant effect on the relocation of molten core and heat-removal capability of the debris bed. Considering its complicate multiphase mechanism, a comprehensive computational tool is needed to reasonably simulate transient particle behavior as well as thermal-hydraulic phenomenon of surrounding fluid phases. The SIMMER program is a successful computer code initially developed as an advanced tool for CDA analysis of LMFRs. It is a multi-velocity-field, multiphase, multicomponent, Eulerian, fluid dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron kinetics model. Until now, the code has been successfully applied in numerical simulations for reproducing key thermal-hydraulic phenomena involved in CDAs as well as performing reactor safety assessment. However, strong interactions between massive solid particles as well as particle characteristics in multiphase flows were not taken into consideration in its fluid-dynamics models. To solve this problem, a new method is developed by combining the discrete element method (DEM) with the multi-fluid models of SIMMER code to reasonably simulate the particle behaviors as well as the thermal-hydraulic phenomena of multiphase fluid flows. In this paper, the coupling method is validated by performing numerical simulations on a series of experiments with cylindrical particle bed in 3D situation. Based on various experimental conditions, Reasonable agreement between simulation results and corresponding experimental data can demonstrate the applicability of the method in reproducing the self-leveling behavior of debris bed. Sensitivity analysis on some model parameters of DEM is also performed to assess their impacts in the simulation. It is expected that the present method can be used as a computational tool to estimate self-leveling process of debris beds as well as the following behaviors in real reactor environment..
66. Nur Asiah Aprianti, Sparisoma Viridi, Zaki Su'ud, Koji Morita, Particle-based simulation of Rayleigh-Taylor instability, 5th International Conference on Advances in Nuclear Science and Engineering, ICANSE 2015 Journal of Physics: Conference Series, 10.1088/1742-6596/799/1/012012, 799, 1, 2017.02, Rayleigh-Taylor instability is a typical benchmark in a computational fluid dynamics, which show interpenetrate materials happened when a heavy liquid is above a lighter liquid. In particle method, Shirakawa et. al. had been proposed a correction term on modelling a buoyancy force to show the phenomena of Rayleigh-Taylor instability (RTI) in the simulation. By adjust a specific value of correction term for a specific mass density ratio, Rayleigh-Taylor instability phenomena had been observed on MPS method. Later, the phenomena is also observed on FVP methods using the same modelling. In this study, several mass density ratio and viscosity ratio of liquids have been proposed as parametric simulation to observe Rayleigh-Taylor instability. The results show the correlations between mass density ratio and viscosity ratio in the specific correction term value of buoyancy model. This results confirmed that the RTI phenomena can be observed in specific mass density ratio..
67. N.A. APRIANTI, S. VIRIDI, Z. SU'UD, K. MORITA, Particle-based simulation of Rayleigh-Taylor instability, Journal of Physics: Conference Series, 799, 012012, 2017.02.
68. Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Ken-ichi Matsuba, Kenji Kamiyama, Tohru Suzuki, Experimental Database for Bed Formation Behaviors of Solid Particles, Proc. of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), N10P1135, 2016.11.
69. LIU XIAOXING, Koji Morita, Shuai Zhang, Numerical Simulation of Jet Breakup in Coolant Using A Mesh-Particle Hybrid Method, Proc. of 10th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS10), N10P1082, 2016.11.
70. Md Abdur Rob Sheikh, Eikaku Son, Motoki Kamiyama, Tohru Morioka, Tatsuya Matsumoto, Koji Morita, Ken-ichi Matsuba, Kenji Kamiyama, Tohru Suzuki, Experimental Investigation on Characteristics of Mixed Particle Debris in Sedimentation and Bed Formation Behavior, Proc. of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), N11P0029, 2016.10.
71. LIU XIAOXING, Koji Morita, Shuai Zhang, Numerical Simulation of Droplet Breakup Using a Mesh-Particle Hybrid Method, Proc. of 11th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-11), N11P0192, 2016.10.
72. Kuniyoshi Takamatsu, Tatsuya Matsumoto, Koji Morita, 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, Annals of Nuclear Energy, 10.1016/j.anucene.2016.05.012, 96, 137-147, 2016.10, A new, highly efficient reactor cavity cooling system (RCCS) with passive safety features and without electrical or mechanical driving requirement is proposed. The RCCS design consists of two continuous closed regions: an ex-reactor pressure vessel region (RPV region) and a cooling region with a heat-transfer surface to ambient air assumed to be 40 (°C). The RCCS uses a novel shape to efficiently remove the heat released from the RPV through radiation and natural convection. Employing air as the working fluid and ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay-heat-removal. In the paper, we address a comparative methodology between a real RCCS (REAL) and a scaled-down heat-removal test facility (SCALE). As an example, the heat flux by radiation of (SCALE) can be the same as that of (REAL) because the two have the same temperatures of the RPV and the RCCS,
TRPV(REAL)
=
TRPV(SCALE)
,
TRCCS(REAL)
=
TRCCS(SCALE)
, and the same view and configuration factors. Next, we also conduct comparisons on natural convection using the Grashof number,
Gr
rRCCS
-
rRPV
. Here, the ratio of (SCALE) to (REAL) in terms of characteristic length is defined as (
rRCCS
-
rRPV
)(SCALE)(
rRCCS
-
rRPV
)(REAL)=1x. When the working fluid in (SCALE) can be pressurized up to
x32
times that of (REAL), (SCALE)'s Grashof number,
Gr
rRCCS
-
rRPV
, can be the same as that of (REAL). Moreover, (SCALE)'s heat flux on the RPV surface as the experimental conditions for obtaining the same Grashof number as that of (REAL) can be determined. The difference between (SCALE) and (REAL) in terms of the heat flux on the RPV surface is (x-1) times (REAL)'s heat flux by natural convection. Thus, (SCALE) will obtain valuable experimental data for demonstrating the new RCCS's performance..
73. LIU XIAOXING, GUO LIANCHENG, Koji Morita, S. ZHANG, Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations, International Journal for Numerical Methods in Fluids, 82, 6, 334-347, 2016.08.
74. B. VEZZONI, M. MARCHETTI, L. ANDRIOLO, F. GABRIELLI, X.-N. CHEN, C. MATZERATH BOCCACCINI, A. RINEISKI, W. MASCHEK, Koji Morita, Tatsumi Arima, SIMMER/PARTISN Analyses of EBR-II Shutdown Heat Removal Tests, Proc. of Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century, 6, 3973-3982, 2016.05.
75. Koji Morita, Tatsuya Matsumoto, Shinpei Nishi, Tatsuya Nishikido, Songbai Cheng, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, A new empirical model for self-leveling behavior of cylindrical particle beds, journal of nuclear science and technology, 10.1080/00223131.2015.1126204, 53, 5, 713-725, 2016.05, During the material relocation phase of core disruptive accidents in sodium-cooled fast reactors, the rapid quenching and fragmentation of molten materials discharged from the reactor core into the lower plenum region can lead to the formation of debris beds. Coolant boiling may lead to leveling of the mound-shaped beds, which changes both the beds' coolability with decay heat in the fuel and the neutronic characteristics. In this study, a series of experiments using simulant materials were performed to develop an experimental database of self-leveling processes of particle beds in a cylindrical system. To simulate the coolant boiling in the beds in the experiments, a gas injection method was used to percolate nitrogen gas uniformly through the base of a bed with a conical-shaped mound. Time variations in bed height during the self-leveling process were measured for different particle sizes, densities and sphericities, and gas injection velocities. Using a dimensional analysis approach, a new model was proposed. This model correlates the experimental data on transient bed height with an empirical equation using a characteristic time for self-leveling development and an equilibrium bed height. The proposed model reasonably predicts the self-leveling development of particle beds..
76. Yoshiharu Tobita, Kenji Kamiyama, Hirotaka Tagami, Ken Ichi Matsuba, Tohru Suzuki, Mikio Isozaki, Hidemasa Yamano, Koji Morita, Liancheng Guo, Bin Zhang, Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors, journal of nuclear science and technology, 10.1080/00223131.2016.1143409, 53, 5, 698-706, 2016.05, The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors (SFRs). In the CDA of SFRs, molten core material relocates to the lower plenum of reactor vessel and may impose significant thermal load on the structures, resulting in the melt-through of the reactor vessel. In order to enable the assessment of this relocation process and prove that IVR of core material is the most probable consequence of the CDA in SFRs, a research program to develop the evaluation methodology for the material relocation behavior in the CDA of SFRs has been conducted. This program consists of three developmental studies, namely the development of the analysis method of molten material discharge from the core region, the development of evaluation methodology of molten material penetration into sodium pool, and the development of the simulation tool of debris bed behavior. The analysis method of molten material discharge was developed based on the computer code SIMMER-III since this code is designed to simulate the multi-phase, multi-component fluid dynamics with phase changes involved in the discharge process. Several experiments simulating the molten material discharge through duct using simulant materials were utilized as the basis of validation study of the physical models in this code. It was shown that SIMMER-III with improved physical models could simulate the molten material discharge behavior, including the momentum exchange with duct wall and thermal interaction with coolant. In order to develop an evaluation methodology of molten material penetration into sodium pool, a series of experiments simulating jet penetration behavior into sodium pool in SFR thermal condition were performed. These experiments revealed that the molten jet was fragmented in significantly shorter penetration length than the prediction by existing correlation for light water reactor conditions, due to the direct contact and thermal interaction of molten materials with coolant. The fragmented core materials form a sediment debris bed in the lower plenum. It is necessary to remove decay heat safely from this debris bed to achieve IVR. A simulation code to analyze the behavior of debris bed with decay heat was developed based on SIMMER-III code by implementing physical models, which simulate the interaction among solid particles in the bed. The code was validated by several experiments on the fluidization of particle bed by two-phase flow. These evaluation methodologies will serve as a basis for advanced safety assessment technology of SFRs in the future..
77. K. TAKAMATSU, Tatsuya Matsumoto, Koji Morita, New Reactor Cavity Cooling System with A Novel Shape and Passive Safety Features, Proc. of International Congress on Advances in Nuclear Power Plants, ICAPP 2016, 2, 1250-1257, 2016.04.
78. Liancheng Guo, Koji Morita, Yoshiharu Tobita, Numerical Simulations of Gas–Liquid–Particle Three-Phase Flows Using a Hybrid Method, Journal of Nuclear Science and Technology, 53, 2, 271-280, 2016.02.
79. Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang, Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations, International Journal for Numerical Methods in Fluids, 10.1002/fld.4220, 2016.02.
80. Xaoxing Liu, Yuki Aramaki, Liancheng Guo, Koji Morita, Numerical Simulation of Gas-Liquid-Solid Three-Phase Flow Using Particle Methods, Journal of Nuclear Science and Technology, http://dx.doi.org/10.1080/00223131.2015.1012132, 52, 12, 1480-1489, 2015.12.
81. 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, EBR-II Passive Safety Demonstration Tests Benchmark Analyses-Phase 2, Proc. of International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015, 4, 3030-3043, 2015.09.
82. Isao Tatewaki, Koji Morita, Hiroshi Endo, A Study on Characteristics of Molten Pool Sloshing in Core Disruptive Accidents of Fast Reactors, Proc. of 23rd International Conference on Nuclear Engineering (ICONE23), ICONE23-1948, 2015.05.
83. Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang, Development of a Hybrid Particle-Mesh Method for Two-Phase Flow Simulations with Phase Change, Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10), NUTHOS10-1137, 2014.12.
84. Yoshiharu Tobita, Kenji Kamiyama, Hirotaka Tagami, Ken-ichi Matsuba, Tohru Suzuki, Mikio Isozaki, Hidemasa Yamano, Koji Morita, Liancheng Guo, Bin Zhang, Development of the Evaluation Methodology for the Material Relocation Behavior in the Core Disruptive Accident of Sodium-Cooled Fast Reactors, Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10), NUTHOS10-1220, 2014.12.
85. Koji Morita, Tatsuya Matsumoto, Syohei Taketa, Sinpei Nishi, Songbai Cheng, Tohru Suzuki, Yoshiharu Tobita, Validation of New Empirical Model for Self-Leveling Behavior of Cylindrical Particle Beds Based on Experimental Database, Proc. of 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-10), NUTHOS10-1299, 2014.12.
86. Xiaoxing Liu, Koji Morita, A Hybrid Particle-Mesh Method for Simulation of Mixed Incompressible and Compressible Flows, Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), N9P0027, 2014.11.
87. Md. Shamsuzzaman, Tatsuya Matsumoto, Motoki Kamiyama, Tohru Morioka, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, Experimental Study on Sedimentation Behavior of Core Debris, Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), N9P0059, 2014.11.
88. Koji Morita, Tatsuya Matsumoto, Yuki Emura, Tatsuhiro Abe, Isao Tatewaki, Hiroshi Endo, Investigation on Sloshing Response of Liquid in a 2D Pool against Hydraulic Disturbance, Proc. of 9th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS9), N9P0033, 2014.11.
89. Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Syohei Taketa, Sinpei Nishi, Tatsuya Nishikido, Bin Zhang, Tatsuya Matsumoto, Koji Morita, An Investigation on Debris Bed Self-Leveling Behavior with Non-Spherical Particles, Journal of Nuclear Science and Technology, 51, 9, 1096-1106, 2014.09.
90. Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita, Numerical Simulation of a Self-Leveling Experiment Using a Hybrid Method, Mechanical Engineering Journal, 1, 4, TEP0024, 2014.08.
91. Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Experimental Study and Empirical Model Development for Self-Leveling Behavior of Debris Bed Using Gas-Injection, Mechanical Engineering Journal, 1, 4, TEP0022, 2014.08.
92. Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita, Validation of a 3D Hybrid CFD-DEM Method Based on a Self-Leveling Experiment, Proc. of 2014 22nd International Conference on Nuclear Engineering (ICONE22), ICONE22-30618, 2014.07.
93. Liancheng Guo, Koji Morita, Yoshiharu Tobita, Numerical Simulation of Gas-Solid Fluidized Beds by Coupling a Fluid-Dynamics Model with the Discrete Element Method, Annals of Nuclear Energy, 72, 31-38, 2014.04.
94. Md. Shamsuzzaman, Bin Zhang, Tatsuhiro Horie, Fusata Fuke, Tatsuya Matsumoto, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, Numerical Study on Sedimentation Behavior of Solid Particles Used as Simulant Fuel Debris, Journal of Nuclear Science and Technology, 51, 5, 681-699, 2014.02.
95. Songbai Cheng, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Evaluation of Debris Bed Self-Leveling Behavior: A Simple Empirical Approach and its Validations, Annals of Nuclear Energy, 63, 188-198, 2014.01.
96. Xiaoxing Liu, Liancheng Guo, Koji Morita, Shuai Zhang, Improved Simulation of a Single Bubble Rising in Stagnant Liquid Using Finite Volume Particle Method, Proc. of 24th International Symposium on Transport Phenomena (ISTP-24), 2013.11.
97. Liancheng Guo, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita, Numerical Simulation of 3D Particulate Flow by Coupling Multi-Fluid Model with Discrete Element Method, Proc. of Joint Research Conference on Supercomputing in Nuclear Applications + Monte Carlo (SNA + MC 2013), A008, 2013.10.
98. Songbai Cheng, Hirotaka Tagami, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Developing A Methodological Framework for Extending An Empirical Model to Predict Self-Leveling Behavior of Debris Beds with Non-Spherical Particles, Proc. of the International Conference on Power Engineering-13 (ICOPE-13), 2013.10.
99. GUO LIANCHENG, Koji Morita, Hirotaka Tagami, Yoshiharu Tobita, Numerical Simulation of Self-leveling Behavior in Debris Bed by a Hybrid Method, Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21), ICONE21-15483, 2013.07.
100. Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Syohei Taketa, Sinpei Nishi, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Recent Knowledge from an Experimental Investigation on Self-Leveling Behavior of Debris Bed, Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21), ICONE21-15595, 2013.07.
101. Yuki Aramaki, Takahito Suzuki, Ichiro Miya, GUO LIANCHENG, Koji Morita, Numerical Simulation of Single Bubble Moving in Stagnant Solid-Liquid Mixture Pool Using Finite Volume Particle Method, Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21), ICONE21-16688, 2013.07.
102. Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yoji Gondai, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Experimental Investigation on Self-Leveling Behavior of Debris Beds Using Gas-Injection, Experimental Thermal and Fluid Science, 48, 110〜121, 2013.07.
103. Md. Shamsuzzaman, Tatsuhiro Horie, Fusata Fuke, Takayuki Kai, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Hirotaka Tagami, Tohru Suzuki, Yoshiharu Tobita, Experimental Evaluation of Debris Bed Characteristics in Particulate Debris Sedimentation Behaviour, Proc. of 2013 21th International Conference on Nuclear Engineering (ICONE21), ICONE21-15693, 2013.07.
104. Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Characteristics of Self-Leveling Behavior of Debris Beds in a Series of Experiments, Nuclear Engineering and Technology, 45, 3, 323-334, 2013.06.
105. Songbai Cheng, Hidemasa Yamano, Tohru Suzuki, Yoshiharu Tobita, Yuya Nakamura, Bin Zhang, Tatsuya Matsumoto, Koji Morita, Empirical Correlations for Predicting the Self-Leveling Behavior of Debris Bed
, Nuclear Science and Techniques, 24, 1, 010602, 2013.02.
106. S. CHENG, H. YAMANO, T. SUZUKI, Y. TOBITA, Y. GONDAI, Y. NAKAMURA, B. ZHANG, T. MATSUMOTO, K. MORITA, An Experimental Study on Self-Leveling Behavior of Debris Beds with Comparatively Higher Gas Velocities, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1003, 2012.12.
107. H. YAMANO, T. SUZUKI, Y. TOBITA, T. MATSUMOTO, K. MORITA, Validation of the SIMMER-IV Severe Accident Computer Code on Three-Dimensional Sloshing Behavior, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1004, 2012.12.
108. M. SHAMSUZZAMAN, T. HORIE, F. FUKE, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, H. TAGAMI, T. SUZUKI, Y. TOBITA, Experimental Investigation of Debris Sedimentation Behavior on Bed Formation Characteristics, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1010, 2012.12.
109. L. GUO, K. MORITA, Y. TOBITA, Numerical Simulation of Bubbling Fluidized Beds by Coupling Multi-Fluid Model with Discrete Element Method, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1015, 2012.12.
110. K. MORITA, T. TAKEDA, W. OHSHIMA, N. APRIANTI, L. GUO, Particle-Based Simulation of Melt Freezing Behavior in Pin Bundle, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1124, 2012.12.
111. N. APRIANTI, T. TAKEDA, I. MIYA, L. GUO, K. MORITA, Analysis of Heat-Transfer and Wall-Failure Behaviors in EAGLE-1 In-Pile Test ID1 using Finite Volume Particle Method, Proc. of 8th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS8), N8P1127, 2012.12.
112. L. GUO, K. MORITA, Y. TOBITA, Numerical Simulation of Three-Phase Flows with Rich Solid Particles by Coupling Multi-Fluid Model with Discrete Element Model, Proc. of 2012 20th International Conference on Nuclear Engineering collocated with ASME 2012 Power Conference (ICONE20-POWER2012), ICONE20- POWER2012-54053, 2012.07.
113. B. ZHANG, T. MATSUMOTO, K. MORITA, H. YAMANO, H. TAGAMI, T. SUZUKI, Y. TOBITA, Numerical Simulation of the Self-Leveling Phenomenon by Modified SIMMER-III, Proc. of 2012 20th International Conference on Nuclear Engineering collocated with ASME 2012 Power Conference (ICONE20-POWER2012), ICONE20- POWER2012-54684, 2012.07.
114. L. GUO, S. ZHANG, K. MORITA, K. FUKUDA, Fundamental Validation of the Finite Volume Particle Method for 3D Sloshing Dynamics, Int. J. Numerical Methods in Fluids, 68, 1, 1-17, 2012.01.
115. K. MORITA, S. ZHANG, S. KOSHIZUKA, Y. TOBITA, H. YAMANO, N. SHIRAKAWA, F. INOUE, H. YUGO, M. NAITOH, H. OKADA, Y. YAMAMOTO, M. HIMI, E. HIRANO, S. SHIMIZU, M. OUE, Detailed Analyses of Key Phenomena in Core Disruptive Accidents of Sodium-cooled Fast Reactors by the COMPASS Code, Nuclear Engineering and Design, 241, 12, 4672-4681, 2011.12.
116. Md. A.M. SONER, Y. HASEGAWA, S. SEO, Y. HIMURO, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Experimental investigation of solid-liquid mixtures freezing behavior in flow channels, Nuclear Engineering and Design, 241, 10, 4223-4235, 2011.10.
117. S. CHENG, Y. TANAKA, Y. GONDAI, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMONO, T. SUZUKI, Y. TOBITA, Experimental Studies and Empirical Models for the Transient Self-Leveling Behavior in Debris Bed, J. Nuclear Science and Technology, 48, 10, 1327-1336, 2011.10.
118. R. SN MAHMUDAH, M. KUMABE, T. SUZUKI, L. GUO, K. MORITA, 3D Simulation of Solid-melt Mixture Flow with Melt Solidification Using a Finite Volume Particle Method
, J. Nuclear Science and Technology, 48, 10, 1300-1312, 2011.10.
119. W. MASCHEK, M. FLAD, C.M. BOCCACCINI, S. WANG, F. GABRIELLI, V. KRIVENTSEV, X.N. CHEN, D. ZHANG, K. MORITA, Prevention and Mitigation of Severe Accident Developments and Recriticalities in Advanced Fast Reactor Systems, Progress in Nuclear Energy, 53, 7, 835-841, 2011.09.
120. T. SUZUKI, L. GUO, R. SN MAHMUDAH, K. MORITA, Numerical Simulation of Effective Viscosity in Solid-Fluid Mixture Flows Using Finite Volume Particle Method, Proc. of 19th International Conference on Nuclear Engineering (ICONE-19), ICONE19-43981, 2011.08.
121. Md. A.M. SONER, Y. HASEGAWA, T. MATSUMOTO, K. MORITA, W. MASCHEK, Simulation of Solid-liquid Multiphase Flows with Fuel Relocation and Freezing Behavior in Pin Bundle Geometry, Proc. of 19th International Conference on Nuclear Engineering (ICONE-19), ICONE19-43982, 2011.08.
122. Md. A.M. SONER, Y. HASEGAWA, T. MATSUMOTO, K. MORITA, W. MASCHEK, Particle Effects on Penetration and Solidification of Flowing Mixed Melts on Metal Structures
, J. Nuclear Science and Technology, 48, 8, 1214-1222, 2011.08.
123. S. CHENG, D. HIRAHARA, Y. TANAKA, Y. GONDAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Experimental Investigation of Bubbling in Particle Beds with High Solid Holdup, Experimental Thermal and Fluid Science, 35, 2, 405-415, 2011.02.
124. B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Experimental Investigation on Self-leveling Behavior in Debris Beds, Nuclear Engineering and Design, 241, 1, 366-377, 2011.01.
125. K. MORITA, H. YAMANO, Y. TOBITA, Development of Heat and Mass Transfer Model for Analysis of Material Relocation Phase in Fast Reactors, Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010, N7P0012, 2010.11.
126. Md. A.M. SONER, Y. HASEGAWA, S. NAKAYAMA, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Experimental Study on Penetration and Freezing Behavior of Solid-liquid Multiphase Flow in Pin Bundle Geometry, Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010, N7P0010, 2010.11.
127. S. CHENG, Y. TANAKA, Y. GONDAI, T. KAI, B. ZHANG, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Experimental Investigation on Self-leveling Behavior in Debris Bed, Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010, N7P0009, 2010.11.
128. R. SN MAHMUDAH, M. KUMABE, W. TORII, I. MIYA, T. TAKEDA, T. SUZUKI, L. GUO, K. MORITA, 3D Simulation of Solid-melt Mixture Flow with Phase Change Using Finite Volume Particle Method, Proc. of 7th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS7), Chuncheon, Korea, Nov. 14-17, 2010, N7P0006, 2010.11.
129. L. GUO, Y. KAWANO, S. ZHANG, T. SUZUKI, K. MORITA, K. FUKUDA, Numerical Simulation of Rheological Behavior in Melting Metal Using Finite Volume Particle Method, J. Nuclear Science and Technology, 47, 11, 1011-1022, 2010.11.
130. Ryodai Nakai, Tohru Suzuki, Kenji Kamiyama, Hiroshi Seino, Kazuya Koyama, Koji Morita, Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (1) Overview of Evaluation Technology Development, Proc. of 8th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-8), N8P0095, 2010.10.
131. 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, Detailed Analyses of Specific Phenomena in Core Disruptive Accidents of Sodium-Cooled Fast Reactors by the COMPASS Code, Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010, ICONE18-29886, 2010.05.
132. S. CHENG, D. HIRAHARA, Y. TANAKA, Y. GONDAI, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANAO, T. SUZUKI, Y. TOBITA, Experimental Study of Bubble Behavior in a Two-Dimensional Particle Bed With High Solid Holdup, Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010, ICONE18-29710, 2010.05.
133. Md. A.M. SONER, S. SEO, Y. HASEGAWA, Y. HIMURO, K. MORITA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Experimental Investigation of Freezing Behavior of Melt/Solid Particles Mixture on to Metal Structure, Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010, ICONE18-29708, 2010.05.
134. L. GUO, S. ZHANG, K. MORITA, K. FUKUDA, Numerical Simulation of 3D Liquid Sloshing Motion With Solid Particles Using Finite Volume Particle Method, Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010, ICONE18-29617, 2010.05.
135. R. SN MAHMUDAH, M. KUMABE, T. SUZUKI, L. GUO, K. MORITA, K. FUKUDA, 3D Simulation of Molten Metal Freezing Behavior Using Finite Volume Particle Method, Proc. of 18th International Conference on Nuclear Engineering (ICONE-18), Xi'an, China, May 17-21, 2010, ICONE18-29198, 2010.05.
136. B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Self-Leveling Onset Criteria in Debris Beds, J. Nuclear Science and Technology, 47, 4, 384-395, 2010.04.
137. S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMAMOTO, Development of a Computational Framework on Fluid-Solid Mixture Flow Simulations for the COMPASS Code, J. Power and Energy Systems, Vol.4, No.1, pp.126-137, 2010.02.
138. 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, Validation for Multi-physics Simulation of Core Disruptive Accidents in Sodium-cooled Fast Reactors by COMPASS Code, Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009, N13P1133, 2009.09.
139. B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Criteria for Occurrence of Self-Leveling in the Debris Bed, Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009, N13P1212, 2009.09.
140. L. GUO, Y. KAWANO, S. ZHANG, K. MORITA, K. FUKUDA, Simulation of Rheological Behavior During Melting Process Using Moving Particle Method, Proc. of 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-13), Kanazawa, Japan, Sept. 27-Oct. 2, 2009, N13P1317, 2009.09.
141. M. Kabir HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Simulation of Molten Metal Penetration and Freezing Behavior in a Seven-pin Bundle Experiment, J. Nuclear Science and Technology, Vol.46, No.8, pp.799-808, 2009.08.
142. Y. YAMAMOTO, E. HIRANO, M. OUE, S. SHIMIZU, N. SHIRAKAWA, S. KOSHIZUKA, K. MORITA, H. YAMANO, Y. TOBITA, 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, Proc. of 17th International Conference on Nuclear Engineering (ICONE-17), Brussels, Belgium, July 12-16, 2009, ICONE17-75521, 2009.07.
143. S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMANOTO, 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, Proc. of 17th International Conference on Nuclear Engineering (ICONE-17), Brussels, Belgium, July 12-16, 2009, ICONE17-75549, 2009.07.
144. 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, Safety Concepts of the 400MWth-Class EFIT Accelerator Driven Transmuter and Considerations for Further Developments, Proc. of 14th International Conference on Emerging Nuclear Energy Systems (ICENES 2009), June 29-July 3, 2009, Ericeira, Portugal, O3.3, 2009.06.
145. P. LIU, X-N. CHEN, F. GABRIELLI, M. FLAD, W. MASCHEK, A. RINEISKI, S. WANG, K. MORITA, M.M. RAHMAN, Y. EGE, Analyses of Transients for 400MWth-Class EFIT Accelerator Driven Transmuter with the SIMMER-III Code, Proc. of International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators (AccApp 2009), May 4-8 2009, Vienna, Austria, ADS/ND-1, 2009.05.
146. 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, COMPASS Code Development and Validation: A Multi-Physics Analysis of Core Disruptive Accidents in Sodium-Cooled Fast Reactors Using Particle Methods, Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP'09), Paper 9329, 2009.05.
147. R. NAKAI, T. SUZUKI, H. YAMANO, H. SEINO, H. ISHIKAWA, K. KAMIYAMA, K. KOYAMA, K. MORITA, Development of Severe Accident Evaluation Technology (Level 2 PSA) for Sodium-cooled Fast Reactors (1) Overview of Evaluation Methodology Development, Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP '09), May 11-15, 2009, Tokyo, Japan, Paper 9117, 2009.05.
148. S. ZHANG, S. KUWABARA, T. SUZUKI, Y. KAWANO, K. MORITA, K. FUKUDA, Simulation of Solid–fluid Mixture Flow Using Moving Particle Methods, J. Computational Physics, Vol.228, Issue 7, pp.2552-2565, 2009.04.
149. S. ZHANG, K. MORITA, N. SHIRAKAWA, Y. YAMAMOTO, Improvement of Basic Fluid Dynamics Models for the COMPASS Code, J. Power and Energy Systems, Vol.3, No.1, pp.313-320, 2009.03.
150. M. KABIR HOSSAIN, Y. HIMURO, K. MORITA, K. NAKAGAWA, T. MATSUMOTO, K. FUKUDA, W. MASCHEK, Investigation of Molten Metal Penetration and Freezing Behavior in a Seven-Pin Channel, Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan, N6P1004, 2008.11.
151. S. ZHANG, L. GUO, K. MORITA, K. FUKUDA, N. SHIRAKAWA, Y. YAMAMOTO, Simulation of Single Bubble Rising up in Stagnant Liquid Pool with Finite Volume Particle Method, Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan, N6P1022, 2008.11.
152. B. ZHANG, T. HARADA, D. HIRAHARA, T. MATSUMOTO, K. MORITA, K. FUKUDA, H. YAMANO, T. SUZUKI, Y. TOBITA, Experimental Study of Self-Leveling Behavior in Debris Bed, Proc. of the Sixth Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS6), November 24-27, 2008, Okinawa, Japan, N6P1042, 2008.11.
153. T. MATSUMOTO, Y. KONO, T. HARADA, D. HIRAHARA, K. MORITA, K. FUKUDA, Transient Behavior of Particle Movement in a Boiling Debris Bed, Proc. of the Seventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Operation and Safety (NUTHOS-7), October 5-9, 2008, Seoul, Korea, No.156, 2008.10.
154. 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, Code development for multi-physics and multi-scale analysis of core disruptive accidents in fast reactors using particle methods, Proc. of 16th Pacific Basin Nuclear Conference (PBNC-16), October 13-18, 2008, Aomori, Japan, 2008.10.
155. M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK, Simulation of Molten Metal Freezing Behavior onto a Structure, Nuclear Engineering and Design, Vol.238, Issue 10, pp.2706-2717, 2008.10.
156. W. MASCHEK, A. RINEISKI, M. FLAD, H. YAMANO, Y. TOBITA, S. FUJITA, T. SUZUKI, K. KAMIYAMA, S. PIGNY, T. CADIOU, K. MORITA, G. BANDINI, The SIMMER Safety Code System and its Validation Efforts for Fast Reactor Application
, Proc. of the International Conference on the Physics of Reactors 2008 (PHYSOR'08), Interlaken, Switzerland, Sept. 14-19, 2008, 2008.09.
157. S. WANG, M. FLAD, W. MASCHEK, P. AGOSTINI, D. PELLINI, G. BANDINI, T. SUZUKI, K. MORITA, Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling, Progress in Nuclear Energy, Vol.50, Issue 2-6, pp. 363-369, 2008.08.
158. 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, Report on Intermediate Results of the IAEA CRP on ‘Studies Of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste’, Energy Conversion and Management, Vol.49, Issue 7, pp.1810-1819, 2008.07.
159. Yuichi YAMANOTO, Etsujo HIRANO, Masaya OUE, Sensuke SHIMIZU, Noriyuki SHIRAKAWA, Seiichi KOSHIZUKA, Koji MORITA, 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, Proc. 16th Int. Conf. on Nuclear Engineering, Orlando, Florida, US, May 11-15, 2008, ICONE16-48485, 2008.05.
160. Shuai ZHANG, Koji MORITA, Noriyuki SHIRAKAWA, Yuichi YAMANOTO, 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, Proc. 16th Int. Conf. on Nuclear Engineering, Orlando, Florida, US, May 11-15, 2008, ICONE16-48475, 2008.05.
161. Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Hidemasa YAMANO, Ikken SATO, Experimental Verification of the Fast Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behavior with Condensation, Nuclear Engineering and Design, Vol.238, Issue 1, pp.49-56, 2008.01.
162. 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, Code Development for Core Disruptive Accidents in Sodium-Cooled Fast Reactors, Proc. of IAEA Topical Meeting on Advanced Safety Assessment Methods for Nuclear Reactors, Daejon, Korea, October 30 - Nomebmebr 2, 2007, 2007.10.
163. M. Mizanur RAHMAN, Tomohiko HINO, Koji MORITA, Tatsuya MATSUMOTO, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHEK, Experimental Investigation of Molten Metal Freezing on to a Structure, Experimental Thermal and Fluid Science, , Vol.32, Issue 1, pp.198-213, 2007.10.
164. 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, The IAEA CRP on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste, Proc. of International Conference GLOBAL 2007, Boise, Idaho, September 9-13, 2007 , 2007.09.
165. Shuai ZHANG, Koji MORITA, Kenji FUKUDA, Noriyuki SHIRAKAWA, A New Algorithm for Surface Tension Model in Moving Particle Methods, Int. J. Numerical Methods in Fluids, Vol.55, Issue 3, pp.225-240, 2007.09.
166. Ping Liu, Xuenong Chen, Andrei Rineiski, Claudia Matzerath Boccaccini, Fabrizio Gabrielli, Werner Maschek, Koji Morita, Fosco Bianchi, First Safety Analyses for an EFIT Type Accelerator Driven Transmuter, Proc. of the Eighth International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'07), Pocatello, ID, July 30-August 2, 2007, 2007.07.
167. 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, Report on Intermediate Results of the IAEA CRP on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste', Proc. of 13th International Conference on Emerging Nuclear Energy Systems (ICENES 2007), Istanbul, Turkey, June 3-8, 2007, 2007.06.
168. Koji MORITA, Vitaly SOBOLEV, Michael FLAD, Critical Parameters and Equation of State for Heavy Liquid Metals, J. Nuclear Materials, Vol.362, pp.227-234, 2007.05.
169. Hidemasa Yamano, Yoshiharu Tobita, Satoshi Fujita, Tohru Suzuki, Kenji Kamiyama, Koji Morita, Werner Maschek, Sylvain Pigny, SIMMER-III: A coupled Neutronics-Thermohydraulics Computer Code for Safety Analysis, Proc. 15th Int. Conf. on Nuclear Engineering, Nagoya, Japan, April 22-26, 2007, ICONE15-10462, 2007.04.
170. Ping LIU, Satoshi YASUNAKA, Tatsuya MATSUMOTO, Koji MORITA, Kenji FUKUDA, Hidemasa YAMANO, Yoshiharu TOBITA, Dynamic Behavior of a Solid Particle Bed in a Liquid Pool, SIMMER-III Code Verification, Nuclear Engineering and Design, Vol.237, No.5, pp.524-535, 2007.03.
171. S. Wang, M. Flad, W. Maschek, P. Agostini, D. Pellini, T. Suzuki, K. Morita , Evaluation of a Steam Generator Tube Rupture Accident in an Accelerator Driven System with Lead Cooling, Proc. the 2nd COE-INES International Symposium on Innovative Nuclear Energy Systems, INES-2, November 26 - 30, 2006, Yokohama, Japan, 2006.11.
172. M. Mizanur RAHMAN, Yoshiyuki EGE, Koji MORITA, Kiyoshi NAKAGAWA, Kenji FUKUDA, Werner MASCHECK, Experimental Simulation of Molten Metal Freezing Behavior onto a Structure with a Reactor Safety Analysis Code, SIMMER-III, Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006, NTHAS5-K005, 2006.11.
173. 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, Multi-Physics and Multi-Scale Simulation for Core Disruptive Accidents in Fast Breeder Reactors, Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006, NTHAS5-F010, 2006.11.
174. Koji MORITA, Tatsuya MATSUMOTO, Kenji FUKUDA, Yoshiharu TOBITA, Ikken SATO, Hidemasa YAMANO, Condensation of a Large-Scale Bubble in Subcooled Liquid: Experimental Verification of the SIMMER-III Code, Proc. of 5th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS5), Jeju, Korea, November 26-29, 2006, NTHAS5-B007, 2006.11.
175. Werner Maschek, Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Claudia Matzerath Boccaccini, Magnus Mori, Koji Morita, Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels, Nuclear Instruments and Methods in Physics Research A, Vol.562, pp.863-866, 2006.06.
176. K.Morita, V.Sobolev, M. Flad, Equation of State for Heavy Liquid Metal Targets, Proc. E-MRS 2006 Spring Meeting, Nice, France, May 29-June 2, 2006, Paper No. XZ7BS, 2006.05.
177. Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano, Thermophysical Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis, J. Nuclear Science and Technology, Vol.43, No. 5, pp.1-11, 2006.05.
178. Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa, An Improved MPS Method for Numerical Simulations of Convective Heat Transfer Problems, Int. J. Numerical Methods in Fluids, Vol.51, No. 1, pp. 31-47, 2006.05.
179. Y. Tobita, Sa. Kondo, H. Yamano, K. Morita, W. Maschek, P. Coste, T. Cadiou, The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments, Nuclear Technology, Vol.153, No.3, pp. 245-263, 2006.03.
180. Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita, Simulation of the Dynamic Behavior of the Solid Particle Bed in a Liquid Pool: Sensitivity of the Particle Jamming and Particle Viscosity Models, J. Nuclear Science and Technology, Vol.43, No. 2, pp.140-149, 2006.02.
181. Kenji Fukuda, Narumi Shikasyo, Tastuya Matsumoto, Koji Morita, 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' -, Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005, Paper No. 317, 2005.10.
182. Xue-Nong Chen, Tohru Suzuki, Andrei Rineiski, Magnus Mori, Clausia Matzerath Boccaccini, Werner Maschek, Koji Morita, Analysis of Transients and Severe Accidents in Accelerator Driven Transmuters (ADTs) of the 800 MWth Class with Fertile-Free Fuels, Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005, Paper No. 152, 2005.10.
183. Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Clausia Matzerath Boccaccini, Werner Maschek, Koji Morita, Analysis of Transients for an IAEA Benchmark on Accelerator Driven Transmuters with Fertile-Free Fuels, Proceedings of International Conference GLOBAL 2005, Nuclear Energy Systems for Future Generation and Global Sustainability, Tsukuba, Japan, October 9-13, 2005, Paper No. 031, 2005.10.
184. 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, SIMMER-III and SIMMER-IV Safety Code Development for Reactors with Transmutation Capability
, 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) , 2005.09.
185. Werner Maschek, Tohru Suzuki, Xue-Nong Chen, Andrei Rineiski, Clausia Matzerath Boccaccini, Magnus Mori, Koji Morita, Analysis of transients for an 800MWth-class accelerator driven transmuter with fertail-free fuels, The Seventh International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp05), Venice, Italy, August 29-September 1, 2005, 10.1016/j.nima.2006.02.073, 562, 2, 863-866, 2005.08.
186. Koji Morita, Wernar Maschek, Michael Flad, Yoshiharu Tobita, Hidemasa Yamano, Thermodynamic Properties of Lead-bismuth Eutectic for Use in Reactor Safety Analysis, Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005, ICONE13-50813, 2005.05.
187. Ping Liu, Satoshi Yasunaka, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Yoshiharu Tobita, Simulation of Multi-phase Flows with Solid Particle Bed in a Water Pool, Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005, ICONE13-50382, 2005.05.
188. Shuai Zhang, Koji Morita, Kenji Fukuda, Noriyuki Shirakawa, Simulation of the Incompressible Flows with the MPS Method, Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005, ICONE13-50166, 2005.05.
189. Wernar Maschek, Xue-Nong Chen, Tohru Suzuki, Andrei Rineiski, Claudia Matzerath Boccaccini, Magnus Mori, Koji Morita, A Review on Safety Issues and Analysis Tools for Accelerator Driven Systems and Transmuters, Proc. 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16-20, 2005, ICONE13-50005, 2005.05.
190. K. Morita, T. Matsumoto, K. Fukuda, Y. Tobita, H. Yamano, I. Sato,, Improvement of a Reactor Safety Analysis Code SIMMER-III for Transient Bubble Behaviors, 6th Int. Conf. on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-6), Nara, Oct. 4-8, 2004, N6P051, 2004.10.
191. M. Mori, W. Maschek, E. Laurien, K. Morita, Monte-Carlo/Simmer-III Reactivity Coefficients Calculations for the SuperCritical Water Fast Reactor, Proceedings of GLOBAL 2003 - Advanced Nuclear Energy and Fuel Cycle Systems, New Orleans, LA, November 16-21, 2003, 87753, 2003.11.
192. Magnus Mori, Werner Maschek, Eckart Laurien, Koji Morita, Monte-Carlo/Simmer-III Reactivity Coefficients Calculations for the SuperCritical Water Fast Reactor, Proceedings of GLOBAL 2003, No. 87753, 2003.11.
193. Akihiro Uchibori, Tatsuya Matsumoto, Koji Morita, Kenji Fukuda, Evaluation of Cooling Capability in a Heated Narrow Flow Passage, J. Nuclear Science and Technology, 10.3327/jnst.40.796, 40, 10, 796-806, Vol. 40, No. 10, pp. 796-806, 2003.10.
194. W. Maschek, T. Suzuki, X. Chen, Mg. Mori, C. Matzerath Boccaccini, M. Flad, K.Morita, Behavior of Transmuter Fuels of Accelerator Driven Systems under Severe Accident Conditions, Proceedings of GENES4/ANP2003, No. 1005, 2003.09.
195. A. Uchibori, Y. Ishimaru, M. Yamashita, T. Matsumoto, R. Akasaka, K. Morita, K. Fukuda, Investigation into Coolability by Two-Phase Flow in Narrow Flow Passages, Proceedings of the Eleventh International Conference on Nuclear Engineering (ICONE-11), No. 36279, 2003.04.
196. K. Morita, K. Fukuda, Y. Tobita, Sa. Kondo, T. Suzuki, W. Maschek, Generalized Modeling of Multicomponent Vaporization/Condensation Phenomena for Multiphase-Flow Analysis, Proceedings of the German-Japanese Workshop on Multi-Phase Flow, Karlsruhe, Germany, August 26-28, 2002, Forschungszentrum Karlsruhe, FZKA 6759, 2003.03.
197. W. Maschek, A. Rineiski, M. Flad, K. Morita, P. Coste, Analysis of severe transient scenarios and proposals for safety improvements for ADS transmuters with dedicated fuel, Nuclear Technology, Vol. 141, No. 2, pp. 186-201, 2003.01.
198. T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Extended verification using multi-bubble condensation experiment, Nuclear Engineering and Design, 10.1016/S0029-5493(02)00350-3, 220, 3, 240-254, Vol. 220, No. 3, pp. 240-254, 2003.01.
199. K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification, Nuclear Engineering and Design, 10.1016/S0029-5493(02)00351-5, 220, 3, 224-239, Vol. 220, No. 3, pp. 224-239, 2003.01.
200. G. Su, K. Morita, K. Fukuda, M. Pidduck, D. Jia, J. Miettinen, Analysis of the critical heat flux in round vertical tubes under low pressure and flow oscillation conditions. Applications of artificial neural network, Nuclear Engineering and Design, 220, 1, 17-35, Vol. 220, No. 1, pp. 17-35, 2003.01.
201. R. Akasaka, N. Shikasho, K. Morita, K. Fukuda, An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference, Greenhouse Gas Control Technologies, J. Gale and Y. Kaya (Eds.), Elsevier Science, 2003, 1019-1024, Vol.II, pp.1019-1024, 2003.01.
202. R. Akasaka, N. Shikasho, K. Morita, K. Fukuda, An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference, Greenhouse Gas Control Technologie, 1019-1024, Volume II, J. Gale and Y. Kaya (Eds.), Elsevier Science Ltd., 2003.01.
203. G. Su, K. Fukuda, K. Morita, M. Pidduck, D. Jia, T. Matsumoto, R. Akasaka, Applications of Artificial Neural Network for the Prediction of Flow Boiling Curves, J. Nuclear Science and Technology, 10.3327/jnst.39.1190, 39, 11, 1190-1198, Vol. 39, No. 11, pp. 1190-1198, 2002.11.
204. Y. Tobita, S. Kondo, H. Yamano, S. Fujita, K. Morita, W. Maschek, P. Coste, S. Pigny, J. Louvet, T. Cadiou, The Development of SIMMER-III, an Advanced Computer Program for LMFR Safety Analysis, 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.
205. R. Akasaka, N. Shikasho, K. Morita, K. Fukuda, An Analytical Method of Constructing Best-Mixed Power Generation Systems Reflecting Public Preference, Proceeding of the Sixth International Conference on Greenhouse Gas Control Technologies (GHGT-6), Kyoto, October 2002, J3-5, 2002.10.
206. G. Su, K. Fukuda, D. Jia, K. Morita, Applications of an Artificial Neural Network in Reactor Thermohydraulic Problem: Prediction of Critical Heat Flux, J. Nuclear Science and Technology, Vol. 39, No. 5, pp. 564-571, 2002.05.
207. A. Uchibori, K. Fukuda, K. Morita, T. Matsumoto, Numerical Prediction of Cooling Capability in Hemispherical Gap Flow Passage for In-vessel Core Retention, Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002, No. 22334, 2002.04.
208. T. Matsumoto, A. Uchibori, R. Akasaka, T. Seki, S. Kaminishi, K. Morita, K. Fukuda, Applicability of Modified Drift Flux Model for Bubbly Flow in 2-D/3-D Rectangular Box with Various Kinds of Obstacles, Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002, No. 22245, 2002.04.
209. K. Morita, T. Matsumoto, R. Akasaka, K. Fukuda, T. Suzuki, Y. Tobita, H. Yamano, Sa. Kondo, Advanced Modeling of Multicomponent Vaporization/Condensation Phenomena for a Reactor Safety Analysis Code SIMMER-III, Proceedings of the Tenth International Conference on Nuclear Engineering (ICONE-10), Arlington, VA, April 14-18, 2002, No. 22229, 2002.04.
210. W. MASCHEK, A. RINEISKI, S. WANG, M. FLAD, K. MORITA , Safety Improvements for ADS Transmuters with Dedicated Fuel
, 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.
211. H. Horie, N. Shirakawa, Y. Tobita, K. Morita, Sa. Kondo, The Effect of Bubble Size on the Radial Distribution of Void Fraction in Two-Phase Flow in a Circular Tube, J. Nuclear Science and Technology, 38, 9, 711-720, Vol. 38, No. 9, pp. 711-720, 2001.09.
212. K. Fukuda, T. Matsumoto, N. Kamesako, A. Uchibori, R. Akasaka, K. Nakagawa, K. Morita, A. Hotta, Applicability of Modified Drift Flux Model for 3-D Channel Bubbly Flow with a Rod Inserted, 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, Vol. 1, pp. 79-86, 2001.06.
213. K. Morita, A. Rineiski, E. Kiefhaber, W. Maschek; M. Flad, G. Rimpault, P. Coste, S. Pigny, Sa. Kondo, Y. Tobita, S. Fujita, Mechanistic SIMMER-III Analyses of Severe Transients in Accelerator Driven Systems (ADS), Proceedings of the Ninth International Conference on Nuclear Engineering (ICONE-9), Nice, France, April 8-12, 2001, No. 150, 2001.04.
214. 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, SIMMER-III Code Development for Analyzing Transients and Accidents in Accelerator Driven Systems (ADS), Proceeding of the fourth International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp00), Washington D.C., US, Nov. 13-15, 2000., pp.131-140, 2000.11.
215. W. Maschek, A. Rineiski, K. Morita, G. Mühing, M. Flad, R.J.M. Konings, Safety Analyses for ADS Cores with Dedicated Fuel and Proposals for Safety Improvements, 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.
216. T. Matsumoto, N. Kamesako, T. Seki, A. Uchibori, R. Akasaka, N. Fujimoto, K. Nakagawa, K. Morita, K. Fukuda, Analytical and Experimental Studies of Two Phase Flows in 2-D rectangular Box with Obstacles inserted, Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000, pp.658-665, 2000.10.
217. A. Uchibori, T. Matsumoto, K. Morita, K. Fukuda, Numerical Study on Thermal Hydraulic Phenomena in a Hemispherical gap under Core Meltdown Accident, Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000, pp.575-580, 2000.10.
218. Y. Tobita, Sa. Kondo, H. Yamano, S. Fujita, K. Morita, W. Maschek, J. Louvet, P. Coste, S. Pigny, Current Status and Application of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, Proceedings of the Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-2), Fukuoka, Japan, October 15-18, 2000, pp.65-72, 2000.10.
219. 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, SIMMER-III Code Development for Accelerator Driven Systems (ADS), Proceedongs of the 6th International CAPRA/CADRA Seminar, Newby Bridge, Great Britain, June 26-28, 2000., 2000.06.
220. N. Fujimoto, N. Kamesako, T. Dohmen, K. Morita, K. Fukuda, A. Hotta, R.C. Yang, Application of the Drift Flux Model to Gas-Liquid Two-phase Flows with Obstacles, Proceedings of the Eighth International Conference on Nuclear Engineering (ICONE-8), Baltimore, MD USA, April 2-6, 2000, No. 8119, 2000.04.
221. H. Horie, N. Shirakawa, Y. Tobita, K. Morita, A Study on the Effect of Bubble Size on the Radial Distribution of Void Fraction in Two-Phase Flow in a Tube, Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, No. 7276, 1999.04.
222. K. Morita, Sa. Kondo, Y. Tobita, W. Maschek, M. Flad, G. Arnecke, P. Coste, Applications of the SIMMER-III Fast Reactor Safety Analysis Code to Thermal Interactions of Melts with Sodium and Water, Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, No. 7250, 1999.04.
223. 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, Current Status and Validation of the SIMMER-III LMFR Safety Analysis Code, Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, No. 7249, 1999.04.
224. Y. Tobita, K. Morita, K. Kawada, H. Niwa, N. Nonaka, Evaluation of CDA Energetics in the Prototype LMFBR with Latest Knowledge and Tools, Proceedings of the Seventh International Conference on Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, No. 7145, 1999.04.
225. K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear, SIMMER-III Applications to Fuel-Coolant Interactions, Nuclear Engineering and Design, Vol. 189, pp. 337-357, 1999.01.
226. W. Maschek, K. Morita, M. Flad, SIMMER-III Analyses of Enhanced Fuel Removal Processes under Core Disruptive Accident Conditions, Proceedings of the Sixth International Conference on Nuclear Engineering (ICONE-6), San Diego, California, May 10-14, 1998, No. 6163, 1998.05.
227. K. Morita, E. A. Fischer, K. Thurnay, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part II: Properties of Fast Reactor Materials, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 193-211, 1998.01.
228. K. Morita, E. A. Fischer, Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis Part I: Analytic Equation-of-State Model, Nuclear Engineering and Design, Vol. 183, No. 3, pp. 177-191, 1998.01.
229. K. Morita, Sa. Kondo, Y. Tobita, D. J. Brear, SIMMER-III Applications to Fuel-Coolant Interactions, 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, pp. 785~802, 1998.01.


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