Masahiro Furuya

J-GLOBAL         Last updated: Oct 5, 2019 at 11:09
 
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Name
Masahiro Furuya
Affiliation
Waseda University
Job title
Deputy Associate Vice President
Degree
Ph.D.(Delft University of Technology)
Other affiliation
Tokyo Institute of Technology

Research Areas

 
 

Academic & Professional Experience

 
Apr 2016
 - 
Today
Visiting Professor, Major in Nuclear Engineering, Department of Transdisciplinary Science and Engineering Graduate School of Environment and Society, Tokyo Institute of Technology
 
Jul 2014
 - 
Today
Deputy Associate Vice President, Nuclear Technology Research Laboratory, Central Research Institute of Electric Power Industry
 

Published Papers

 
Riichiro Okawa, Masahiro Furuya
Nuclear Engineering and Design   355 110357   Dec 2019   [Refereed]
Toshiki Kondo, Hiroaki Muta, Ken Kurosaki, Florian Kargl, Akifumi Yamaji, Masahiro Furuya, Yuji Ohishi
Heliyon   5(7) e02049   Jul 2019   [Refereed]
Masahiro Furuya, Hiroki Takiguchi, Riichiro Okawa, Takahiro Arai
Annals of Nuclear Energy   129 207-213   Jul 2019   [Refereed]
Masahiro Furuya, Riichiro Okawa, Takahiro Arai, Hiroki Takiguchi, Kenetsu Shirakawa
Nuclear Engineering and Design   341 38-45   Jan 2019   [Refereed]
Arai T, Furuya M, Kanai T, Shirakawa K.
Experimental Thermal and Fluid Science   60 337-345   Jan 2015   [Refereed]

Misc

 
Takahiro Arai, Masahiro Furuya, Hiroki Takiguchi, Yoshihisa Nishi, Kenetsu Shirakawa
Flow Measurement and Instrumentation   69    Oct 2019
© 2019 Elsevier Ltd Void fraction (i.e., the volume fraction occupied by gas) is a key parameter for determining the coolability and neutron-moderating performance of a water-cooled nuclear reactor. To develop computational multi-fluid dynamics mo...
Takahiro Arai, Masahiro Furuya, Hiroki Takiguchi, Kenetsu Shirakawa
International Conference on Nuclear Engineering, Proceedings, ICONE   2019-May    May 2019
Copyright © 2018-2019 by JSME When boiling occurs in a pool or gas is injected into a stagnant water pool, the actual liquid level, i.e., the two-phase mixture level, becomes higher than the original liquid level, i.e., the collapsed water level, ...
Masafumi Katta, Guangtao Duan, Akifumi Yamaji, Masahiro Furuya
International Conference on Nuclear Engineering, Proceedings, ICONE   2019-May    May 2019
Copyright © 2019 by JSME In a postulated sever accident of a light water reactor (LWR), molten core debris (corium) may breach the reactor pressure vessel and be released to the ex-vessel containment floor. A core catcher manages ex-vessel corium ...
Riichiro Okawa, Masahiro Furuya
Nuclear Engineering and Design   346 97-111   May 2019
© 2019 Elsevier B.V. Numerical analyses were conducted to replicate several tests for simulating a double-ended cold-leg large break loss-of-coolant accident (LBLOCA) in the Loss-of-Fluid Test (LOFT) using the TRACE (version 5/patch level 4) code...
山路哲史, 古谷正裕, 大石佑治, JUBAIDAH, DUAN Guangtao
日本原子力学会春の年会予稿集(CD-ROM)   2019 ROMBUNNO.2I18   Mar 2019