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研究成果 1984 2019

  • 1135 引用
  • 20 h指数
  • 91 記事
  • 30 会議での発言
  • 7 論文
  • 1 評論記事
フィルター
会議での発言
2017

Benchmark study on realized random packing model for coated fuel particles of HTTR using MCNP6

Quan, H. H., Morita, K., Honda, Y., Fujimoto, N. & Takada, S., 1 1 2017, 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP, (2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings).

研究成果: 著書/レポートタイプへの貢献会議での発言

High temperature engineering
Coated fuel particles
Utility programs
Geometry
High temperature reactors
2016

New reactor cavity cooling system with a novel shape and passive safety features

Takamatsu, K., Matsumoto, T. & Morita, K., 1 1 2016, International Congress on Advances in Nuclear Power Plants, ICAPP 2016. American Nuclear Society, 巻 2. p. 1250-1257 8 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

Cooling systems
Test facilities
High temperature gas reactors
Grashof number
Natural convection
1 引用 (Scopus)

Simmer/partisn analyses of EBR-II shutdown heat removal tests

Vezzoni, B., Marchetti, M., Andriolo, L., Gabrielli, F., Chen, X. N., Matzerath Boccaccini, C., Rineiski, A., Maschek, W., Morita, K. & Arima, T., 1 1 2016, Physics of Reactors 2016, PHYSOR 2016: Unifying Theory and Experiments in the 21st Century. American Nuclear Society, 巻 6. p. 3973-3982 10 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

shutdowns
heat
breeder reactors
Breeder reactors
research projects
2015
4 引用 (Scopus)

EBR-II passive safety demonstration tests benchmark analyses-phase 2

Briggs, L., Hu, W., Su, G. H., Vezzoni, B., Del Nevo, A., Monti, S., Sui, D., Maas, L., Sarathy, U. P., Petruzzi, A., Zanino, R., Ohira, H., Mochizuki, H., Morita, K., Choi, C., Shin, A., Stempniewicz, M., Rtishchev, N., Zhang, Y. & Truong, B., 1 1 2015, International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015. American Nuclear Society, p. 3030-3043 14 p. (International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015; 巻数 4).

研究成果: 著書/レポートタイプへの貢献会議での発言

safety
shutdowns
Demonstrations
heat
breeder reactors
2014

Development of assessment method for a self-leveling behavior of debris bed and analyses of experiments

Hirotaka, T., Songbai, C., Yoshiharu, T., Liancheng, G., Bin, Z. & Morita, K., 1 1 2014, Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security. American Society of Mechanical Engineers (ASME), 巻 3.

研究成果: 著書/レポートタイプへの貢献会議での発言

Debris
Experiments
Fast reactors
Sodium
Boiling liquids

Validation of a 3D hybrid cfd-dem method based on a self-leveling experiment

Guo, L., Morita, K., Tagami, H. & Tobita, Y., 1 1 2014, Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. American Society of Mechanical Engineers (ASME), 巻 4.

研究成果: 著書/レポートタイプへの貢献会議での発言

Core disruptive accidents
Debris
Fast reactors
Multiphase flow
Hydraulics
2013

A methodological study on extending an empirical model to predict self-leveling behavior of debris beds with non-spherical particles

Cheng, S., Tagami, H., Yamano, H., Suzuki, T., Tobita, Y., Nakamura, Y., Zhang, B., Matsumoto, T. & Morita, K., 2013, International Conference on Power Engineering 2013, ICOPE 2013. Japan Society of Mechanical Engineers

研究成果: 著書/レポートタイプへの貢献会議での発言

Debris
Particle interactions
Core disruptive accidents
Fast reactors
Pressure drop
8 引用 (Scopus)

Experimental evaluation of debris bed characteristics in particulate debris sedimentation behaviour

Shamsuzzaman, M., Horie, T., Fuke, F., Kai, T., Zhang, B., Matsumoto, T., Morita, K., Tagami, H., Suzuki, T. & Tobita, Y., 1 1 2013, Beyond Design Basis Events; Student Paper Competition. American Society of Mechanical Engineers (ASME), (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 6).

研究成果: 著書/レポートタイプへの貢献会議での発言

Sedimentation
Debris
Nozzles
Core disruptive accidents
Stainless steel
1 引用 (Scopus)

Numerical simulation of self-leveling behavior in debris bed by a hybrid method

Guo, L., Morita, K., Tagami, H. & Tobita, Y., 2013, Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes. American Society of Mechanical Engineers (ASME), 巻 3.

研究成果: 著書/レポートタイプへの貢献会議での発言

Core disruptive accidents
Debris
Fast reactors
Computer simulation
Fluid dynamics

Numerical simulation of single bubble moving in stagnant solidliquid mixture pool using finite volume particle method

Aramaki, Y., Suzuki, T., Miya, I., Guo, L. & Morita, K., 1 1 2013, Beyond Design Basis Events; Student Paper Competition. American Society of Mechanical Engineers (ASME), (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 6).

研究成果: 著書/レポートタイプへの貢献会議での発言

Bubbles (in fluids)
Computer simulation
Liquids
Flow simulation
Fluids
1 引用 (Scopus)

Recent knowledge from an experimental investigation on self-leveling behavior of debris bed

Cheng, S., Yamano, H., Suzuki, T., Tobita, Y., Nakamura, Y., Taketa, S., Nishi, S., Zhang, B., Matsumoto, T. & Morita, K., 1 1 2013, Thermal Hydraulics. American Society of Mechanical Engineers (ASME), (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 4).

研究成果: 著書/レポートタイプへの貢献会議での発言

Fast reactors
Debris
Core disruptive accidents
Flow rate
Nuclear energy
2012
2 引用 (Scopus)

Numerical simulation of the self-leveling phenomenon by modified SIMMER-III

Zhang, B., Matsumoto, T., Morita, K., Yamano, H., Tagami, H., Suzuki, T. & Tobita, Y., 1 1 2012, 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012. 1 版 American Society of Mechanical Engineers (ASME), p. 751-760 10 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 5, 番号 1).

研究成果: 著書/レポートタイプへの貢献会議での発言

Debris
Computer simulation
Core disruptive accidents
Sodium
Rapid quenching
4 引用 (Scopus)

Numerical simulation of three-phase flows with rich solid particles by coupling multi-fluid model with discrete element method

Guo, L., Morita, K. & Tobita, Y., 2012, 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference, ICONE 2012-POWER 2012. 1 版 巻 4. p. 371-382 12 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

Core disruptive accidents
Finite difference method
Multiphase flow
Fluids
Computer simulation
2010

3D simulation of molten metal freezing behaviour using finite volume particle method

Mahmudah, R. S. N., Kumabe, M., Suzuki, T., Guo, L. C., Morita, K. & Fukuda, K., 12 1 2010, 18th International Conference on Nuclear Engineering, ICONE18. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 2).

研究成果: 著書/レポートタイプへの貢献会議での発言

Liquid metals
Freezing
Channel flow
Fluid dynamics
Metals

Detailed analyses of specific phenomena in core disruptive accidents of sodium-cooled fast reactors by the compass code

Morita, K., Zhang, S., Arima, T., Koshizuka, S., Tobita, Y., Yamano, H., Ito, T., Shirakawa, N., Inoue, F., Yugo, H., Naitoh, M., Okada, H., Yamamoto, Y., Himi, M., Hirano, E., Shimizu, S. & Oue, M., 12 1 2010, 18th International Conference on Nuclear Engineering, ICONE18. PARTS A AND B 版 p. 855-863 9 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 4, 番号 PARTS A AND B).

研究成果: 著書/レポートタイプへの貢献会議での発言

Core disruptive accidents
Fast reactors
Molten materials
Sodium
Freezing
1 引用 (Scopus)

Experimental investigation of freezing behavior of melt/solid particles mixture on to metal structure

Malek Soner, M. A., Seo, S., Hasegawa, Y., Himuro, Y., Morita, K., Matsumoto, T., Fukuda, K. & Maschek, W., 12 1 2010, 18th International Conference on Nuclear Engineering, ICONE18. 巻 2.

研究成果: 著書/レポートタイプへの貢献会議での発言

Freezing
Metals
Liquid metals
Molten materials
Volume fraction
11 引用 (Scopus)

Experimental study of bubble behavior in a two-dimensional particle bed with high solid holdup

Cheng, S., Hirahara, D., Tanaka, Y., Gondai, Y., Matsumoto, T., Morita, K., Fukuda, K., Yamano, H., Suzuki, T. & Tobita, Y., 12 1 2010, 18th International Conference on Nuclear Engineering, ICONE18. PARTS A AND B 版 p. 697-704 8 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 4, 番号 PARTS A AND B).

研究成果: 著書/レポートタイプへの貢献会議での発言

Bubbles (in fluids)
Liquids
Core disruptive accidents
Experiments
Nitrogen
1 引用 (Scopus)

Numerical simulation of 3D liquid sloshing motion with solid particles using finite volume particle method

Guo, L. C., Zhang, S., Morita, K. & Fukuda, K., 12 1 2010, 18th International Conference on Nuclear Engineering, ICONE18. PARTS A AND B 版 p. 585-592 8 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 4, 番号 PARTS A AND B).

研究成果: 著書/レポートタイプへの貢献会議での発言

Liquid sloshing
Computer simulation
Molten materials
Liquid metal cooled reactors
Liquids
2009
2 引用 (Scopus)

Analyses of transients for 400MWth-class EFIT accelerator driven transmuter with the SIMMER-III code

Liu, P., Chen, X. N., Gabrielli, F., Flad, M., Maschek, W., Rineiski, A., Wang, S., Morita, K., Rahman, M. M. & Ege, Y., 12 1 2009, International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators. (International Topical Meeting on Nuclear Research Applications and Utilization of Accelerators).

研究成果: 著書/レポートタイプへの貢献会議での発言

Particle accelerators
Accidents
Steam generators
Lead
Actinides
12 引用 (Scopus)

Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development

Nakai, R., Suzuki, T., Yamano, H., Seino, H., Ishikawa, H., Kamiyama, K., Koyama, K. & Morita, K., 1 1 2009, International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009. Atomic Energy Society of Japan, p. 1110-1119 10 p. (International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009; 巻数 2).

研究成果: 著書/レポートタイプへの貢献会議での発言

Fast reactors
Accidents
Sodium
Relocation
3 引用 (Scopus)

Next generation safety analysis methods for SFRS (3) thermal hydraulics models of Compass code and experimental analyses

Yamamoto, Y., Hirano, E., Oue, M., Shimizu, S., Shirakawa, N., Koshizuka, S., Morita, K., Yamano, H. & Tobita, Y., 2009, Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. 巻 5. p. 409-418 10 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

Hydraulic models
Core disruptive accidents
Heat problems
Hydraulic structures
Fast reactors
6 引用 (Scopus)

Next generation safety analysis methods for SFRS (4) development of a computational framework on fluid-solid mixture flow simualtions for the COMPASS code

Zhang, S., Morita, K., Shirakawa, N. & Yamamoto, Y., 2009, Proceedings of the 17th International Conference on Nuclear Engineering 2009, ICONE17. 巻 5. p. 465-471 7 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

Fluids
Flow simulation
Core disruptive accidents
Fast reactors
Sodium
2008
3 引用 (Scopus)

R & D of the next generation safety analysis methods for fast reactors with new computational science and technology (2) development and verification of thermo-hydrodynamics module of the compass code

Yamamoto, Y., Hirano, E., Oue, M., Shimizu, S., Shirakawa, N., Koshizuka, S. & Morita, K., 12 1 2008, 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. p. 359-367 9 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 2).

研究成果: 著書/レポートタイプへの貢献会議での発言

Fast reactors
Hydrodynamics
Core disruptive accidents
Heat problems
Hydraulic structures
3 引用 (Scopus)

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

Zhang, S., Morita, K., Shirakawa, N. & Yamamoto, Y., 12 1 2008, 2008 Proceedings of the 16th International Conference on Nuclear Engineering, ICONE16. p. 345-350 6 p. (International Conference on Nuclear Engineering, Proceedings, ICONE; 巻数 2).

研究成果: 著書/レポートタイプへの貢献会議での発言

Fast reactors
Fluid dynamics
Dynamic models
Core disruptive accidents
Fluids
4 引用 (Scopus)

The SIMMER safety code system and its validation efforts for fast reactor application

Maschek, W., Rineiski, A., Flad, M., Liu, P., Chen, X. N., Tobita, Y., Yamano, H., Suzuki, T., Fujita, S., Kamiyama, K., Pigny, S., Cadiou, T., Morita, K. & Bandini, G., 1 1 2008, International Conference on the Physics of Reactors 2008, PHYSOR 08. Paul Scherrer Institut, p. 2370-2378 9 p. (International Conference on the Physics of Reactors 2008, PHYSOR 08; 巻数 3).

研究成果: 著書/レポートタイプへの貢献会議での発言

Codes (standards)
Fast reactors
safety
reactors
accidents
2007
2 引用 (Scopus)

First safety analyses for an EFIT type Accelerator Driven Transmuter

Liu, P., Chen, X., Rineiski, A., Matzerath Boccaccini, C., Gabrielli, F., Maschek, W., Morita, K. & Bianchi, F., 12 1 2007, 8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07. p. 552-559 8 p. (8th International Topical Meeting on Nuclear Applications and Utilization of Accelerators, ACCAPP'07).

研究成果: 著書/レポートタイプへの貢献会議での発言

Particle accelerators
Accidents
Neutron sources
Conceptual design
Coolants

Report on intermediate results of the IAEA CRP on 'studies of advanced reactor technology options for effective incineration of radioactive waste'

Maschek, W., Stanculescu, A., Arien, B., Bai, Y., Chabert, C., Chebeskov, A. A., Chen, X., Da Cruz, D. F., Dekoussar, V., Devan, K., Dulla, S., Gopalakrishnan, V., Feynberg, O., Harish, R., Ignatiev, V., Kópházi, J., Li, J., Malambu, E., Mohanakrishnan, P., Morita, K. および18人, Pandikumar, G., Peneliau, Y., Ravetto, P., Rineiski, A., Schikorr, M., Srivenkatesan, R., Subbotin, V., Surenkov, A., Szieberth, M., Taczanowski, S., Tuček, K., Vertes, P., Vorotyntsev, M., Uhlíř, J., Wider, H., Wu, Y., Zakirov, R. & Zheng, S., 12 1 2007, 13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007. p. 598-610 13 p. (13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007; 巻数 2).

研究成果: 著書/レポートタイプへの貢献会議での発言

Waste incineration
Radioactive wastes
Bearings (structural)
Waste utilization
Fast reactors
8 引用 (Scopus)

The IAEA CRP on studies of advanced reactor technology options for effective incineration of radioactive waste

Maschek, W., Stanculescu, A., Arien, B., Bai, Y., Chabert, C., Chebeskov, A., Chen, X., Da Cruz, D. F., Dekoussar, V., Devan, K., Dulla, S., Gopalakrishnan, V., Feynberg, O., Harish, R., Ignatiev, V., Kópházi, J., Li, J., Malambu, E., Mohanakrishnan, P., Morita, K. および18人, Pandikumar, G., Peneliau, Y., Ravetto, P., Rineiski, A., Schikorr, M., Srivenkatesan, R., Subbotin, V., Surenkov, A., Szieberth, M., Taczanowski, S., Tuček, K., Vertes, P., Vorotyntsev, M., Uhlíř, J., Wider, H., Wu, Y., Zakirov, R. & Zheng, S., 12 1 2007, GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems. p. 1155-1164 10 p. (GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems).

研究成果: 著書/レポートタイプへの貢献会議での発言

Waste incineration
Radioactive wastes
Bearings (structural)
Waste utilization
Fast reactors
2003
5 引用 (Scopus)

Monte-Carlo/Simmer-III reactivity coefficients calculations for the supercritical water fast reactor

Mori, M., Maschek, W., Laurien, E. & Morita, K., 12 1 2003, Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy. p. 1754-1762 9 p. (Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy).

研究成果: 著書/レポートタイプへの貢献会議での発言

Water cooled reactors
Fast reactors
Water
Loss of coolant accidents
Accidents
2002

Applicability of modified drift flux model for bubbly flow in 2-D/3-D rectangular box with various kinds of obstacles

Matsumoto, T., Uchibori, A., Akasaka, R., Seki, T., Kaminishi, S., Morita, K. & Fukuda, K., 2002, International Conference on Nuclear Engineering, Proceedings, ICONE. 巻 3. p. 375-382 8 p.

研究成果: 著書/レポートタイプへの貢献会議での発言

Two phase flow
Fluxes
Gases
Nitrogen
Perforated plates