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Overview laboratory

In the present thermal design of nuclear reactors, many composition equations which specify the thermal-hydraulic phenomenon in a nuclear reactor are derived based on the experimental data obtained by mock-up test facilities. Moreover, the present thermal design of nuclear reactors is performed using those composition equations.
However, in such a case, a large amount of fund is needed at construction of experimental facilities. Furthermore, many human resources are required for experimental studies. Moreover, several years are required of acquisition of experimental data.
Then, this group is developing a new thermal design method of the nuclear reactors based on large-scale simulations by utilizing supercomputers for the purpose of the realization of an efficient thermal design of the nuclear reactors.




News

T. Misawa, et al., Development of an Analytical Method on Water-Vapor Boiling Two-Phase FlowCharacteristics in BWR Fuel Assemblies Under Earthquake Condition, Nuclear Reactor, Intech, (2012)

K.Takase, et al., Numerical Visualization on Melting and Solidification of Micron-sized Metallic Particles by Laser Irradiation, Quarterly Journal of the Japan Welding Society 、Vol.29, No.3,(2011) pp43-47 (in Japanese)

T. Nakatsuka, et al., Study on Effect of Local Power Distribution of Fuel Assembly on Critical Power of Reduced-Moderation Water Reactor (RMWR), Transactions of the Atomic Energy Society of Japan, Vol 9, No. 2, (2010) (in Japanese)

H. Yoshida, T. Misawa, T. Suzuki and K.Takase, Current Status of Development of Thermal Hydraulic Design Method for Accelerator Driving System in JAEA, Proc. of TCADS1, (2010)

H. Yoshida, H. Hosoi, T. Suzuki and K. Takase, Development of Advanced Two-fluid Model for Boiling Two-phase Flow in Rod Bundles, Proc. of ICONE18, ICONE18-30219, (2010)

T. Nakatsuka, et al., Numerical Simulations on Turbulent Heat Transfer Characteristics of Supercritical Pressure Fluids, IMECE2009-12710, USA, (2009)

K. Takase, et al., Computational Simulations on Melting Process on Fine Metal Powders with Laser Irradiation Welding, IMECE2009-13219, USA, (2009)

T. Misawa, T. Nakatsuka, H. Yoshida, K. Takase, K. Ezato, Y. Seki, M. Dairaku, S. Suzuki, M. Enoeda, Heat Transfer Experiments and Numerical Analysis of Supercritical Pressure Water in Seven-rod Test Bundle, Proc. of NURETH-13, N13P1437 (2009)


Information

Involvement in the Innovative and Viable Nuclear Energy Technology (IVNET) Development Project, "Development of Supercritical Water-Cooled Reactor in GIF Collaboration (Phase-I)", funded by the Ministry of Economy, Trade and Industry (METI) in cooperation with other organizations since FY 2008. Here, our group takes charge of development of a thermal-hydraulic analysis method in SCWR by CFD. Please refer the following WEB site:
http://www.iae.or.jp/KOUBO/innovation/theme/h20/H20_b3.html

Japan science and technology agency, Nnuclear fundamental strategy research initiative project, Strategic nuclear energy joint research program, “Study on the advancement in detailed prediction technology of two-phase flow at addition of earthquake acceleration,” (2010).