Konomo Sanokawa
Japan Atomic Energy Research Institute
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Featured researches published by Konomo Sanokawa.
Nuclear Technology | 1984
Kenji Kikuchi; Hideo Kaburaki; Konomo Sanokawa; Katsuyuki Kawaguchi; Masaaki Nemoto; Shintaro Watanabe
In a very high temperature gas-cooled reactor developed at the Japan Atomic Energy Research Institute, reactor components, such as heat transfer tubes (Hastelloy-XR) of an intermediate heat exchang...
Journal of Nuclear Science and Technology | 1979
Masahiro Seki; Masuro Ogawa; Hiroshi Kawamura; Hiroshi Maekawa; Konomo Sanokawa
A cooling system of a stationary target for the Fusion Neutronics Source (FNS) has been designed to satisfy the structural, thermal and hydraulic requirements. Two square tubes for ion beam and for cooling water were concentrically placed and the target was mounted on the top of the beam guide tube. The end plate of the outer tube was devised to be removable for easier replacement of the target. In order to test the cooling capability of the system, dummy target assemblies with electical heaters were used in the experiment of heat transfer in place of using an accelerator. Correlations of heat transfer and head loss were obtained experimentally as a function of Reynolds number. The extrapolation of the data has shown that for the present target system, about 2.3 kW is the maximum power for the beam in diameter of 15 mm. This value was sufficiently large compared with the required heat load of FNS.
Nuclear Engineering and Design | 1983
Kenji Kikuchi; Toshimitsu Yokobori; Konomo Sanokawa; Yoshizo Okamoto; Takeo Yokobori
Abstract A very high-temperature gas-cooled reactor (VHTR) has been developed by Japan Atomic Energy Research Institute and its core consists of so-called fuel blocks, removable reflector blocks and so on. These graphite blocks are supported by thin cylindrical graphite bars called support posts. These posts are in contact with the blocks through hemispherical seats to absorb the relative displacement of blocks by small inclination or rotation of the posts. Stress distributions and stress concentration coefficients of the support post under the reactor core weight are analysed by means of photoelastic experiment and compared with two-dimensional calculation by using the finite element method. The following are the conclusions we have derived: 1. (1) Stress concentration coefficients of the post are expressed uniquely as a function of Ed( 1 r p − 1 r p ) σ g regardless of the shapes of model and material properties. 2. (2) Inclination of the post caused by small rotation has little effect on the stress concentration coefficients.
American Society of Mechanical Engineers, Heat Transfer Division, (Publication) HTD | 1980
Kenji Fukuda; Yasuyuki Takata; Shu Hasegawa; Hiroaki Shimomura; Konomo Sanokawa
Journal of Nuclear Science and Technology | 1975
Hiroshi Kawamura; Masahiro Seki; Yasuaki Shiina; Konomo Sanokawa
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 1991
Sadao Fujii; Norio Akino; Makoto Hishida; Hiroshi Kawamura; Konomo Sanokawa
Archive | 1982
Yasuyuki Takata; Kenji Fukuda; Shu Hasegawa; Kengo Iwashige; Hiroaki Shimomura; Konomo Sanokawa
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 1985
Kenji Fukuda; Takashi Fukuda; Tetsuzo Yamamoto; Shu Hasegawa; Ryozo Echigo; Konomo Sanokawa
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 1982
Yasuyuki Takata; Kenji Fukuda; Shu Hasegawa; Kengo Iwashige; Hiroaki Shimomura; Konomo Sanokawa
Nippon Genshiryoku Gakkaishi/Journal of the Atomic Energy Society of Japan | 1981
Yasuyuki Takata; Kenji Fukuda; Shu Hasegawa; Hiroaki Shimomura; Konomo Sanokawa