Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Kashika Joho Gakkai-Shi, 35(Suppl.2), p.59 - 60, 2015/09
no abstracts in English
Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Nihon Kikai Gakkai Dai-27-Kai Keisan Rikigaku Koenkai Rombunshu (CD-ROM), 2 Pages, 2014/11
no abstracts in English
Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Nihon Kikai Gakkai Dai-26-Kai Keisan Rikigaku Koenkai Rombunshu (CD-ROM), p.703_1 - 703_2, 2013/11
no abstracts in English
Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Kashika Joho Gakkai-Shi, 32(Suppl.2), p.239 - 240, 2012/10
In the thermal-hydraulic design of supercritical water-cooled reactors, it is required to establish a thermal-hydraulic analysis method which can simulate the heat transfer and fluid flow characteristics of supercritical fluids precisely. A crossing flow is a phenomenon in which the fluid flowing through the inside of a fuel bundle in the perpendicular direction moves between subchannels to a transverse direction. The crossing flow influences the removal heat of a reactor core greatly. In the present study, results of the preliminary crossing flow simulation are described.
Kitamura, Tatsuaki*; Sakamoto, Kensaku; Takase, Kazuyuki
Kashika Joho Gakkai-Shi, 30(Suppl.2), p.359 - 360, 2010/10
no abstracts in English
Nomura, Akira*; Kitamura, Naoto*; Saito, Akira*; Sakamoto, Tatsuaki*; Takebe, Hiromichi*; Kobayashi, Hidekazu; Amamoto, Ippei; Nakamura, Hiroki*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
no journal, ,
no abstracts in English