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Takeda, Tetsuaki*; Inagaki, Yoshiyuki; Aihara, Jun; Aoki, Takeshi; Fujiwara, Yusuke; Fukaya, Yuji; Goto, Minoru; Ho, H. Q.; Iigaki, Kazuhiko; Imai, Yoshiyuki; et al.
High Temperature Gas-Cooled Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.5, 464 Pages, 2021/02
As a general overview of the research and development of a High Temperature Gas-cooled Reactor (HTGR) in JAEA, this book describes the achievements by the High Temperature Engineering Test Reactor (HTTR) on the designs, key component technologies such as fuel, reactor internals, high temperature components, etc., and operational experience such as rise-to-power tests, high temperature operation at 950
C, safety demonstration tests, etc. In addition, based on the knowledge of the HTTR, the development of designs and component technologies such as high performance fuel, helium gas turbine and hydrogen production by IS process for commercial HTGRs are described. These results are very useful for the future development of HTGRs. This book is published as one of a series of technical books on fossil fuel and nuclear energy systems by the Power Energy Systems Division of the Japan Society of Mechanical Engineers.
SRShimomura, Koichiro*; Kadono, Ryosuke*; Nishiyama, Kusuo*; Watanabe, Isao*; Suzuki, Takao*; Pratt, F.*; Oishi, Kazuki; Mizuta, Masashi*; Saito, Mineo*; Chow, K. H.*; et al.
Physica B; Condensed Matter, 376-377, p.444 - 446, 2006/04
Times Cited Count：1 Percentile：6.64(Physics, Condensed Matter)Tsai, H.*; Allen, T. R.*; Cole, J. I.*; Strain, R. V.*; Yoshitake, Tsunemitsu; Donomae, Takako; Akasaka, Naoaki; Mizuta, Shunji; Ukai, Shigeharu; Miyakawa, Shunichi
JNC TY9400 2001-025, 117 Pages, 2001/07
JNC-TY9400-2001-025.pdf:6.94MB
None
Kuwabara, K.*; Kurishita, Hiroaki*; Ukai, Shigeharu; Narui, Makoto*; Mizuta, Shunji; Yamazaki, M.*; Kayano, H.*
Journal of Nuclear Materials, 258-263(Part 2), p.1236 - 1241, 1998/10
Times Cited Count：29 Percentile：88.57(Materials Science, Multidisciplinary)None
*; Mizuta, H.; *; *; Hirasawa, Masayoshi; *; Uruwashi, Shinichi*
PNC TN841 75-03, 203 Pages, 1975/01
no abstracts in English
Drop ExperimentMizuta, H.; Hirabayashi, F.*; Yokozawa, Naoki; Fukushima, Y.*
PNC TN841 74-51, 50 Pages, 1974/12
A series of 30 experiments were performed to examine the fragmentation characteristics of Sodium-Fuel Interaction by dropping molten UO into sodium. In this experiment, annular UO pellets were heated by the center line heating of tungsten rod, and the molten UO droplets fell into the sodium tank. The fragmentations of the droplets on the surface of liquid sodium were photographed with high speed camera at 500-2000 pictures/sec. The Pressure and temperature of sodium tank were measured. The particle characteristics of the UO residue was examined on the particle size distribution, the particle surface condition, and the grain characteristic of the particles for the fragmentation mechanism. These examination indicates that the UO particles can be assumed to be spherical and to have the log-normal distribution function. The most pessimistic particle size distribution at present can be represented by the equation. Where f/supi(D)dD=weight percent of particles in size range D to D+
Koizumi, Masumichi; Furuya, Hirotaka; *; Tachibana, Toshimichi; *; Mizuta, H.; *;
PNC TN841 74-25, 145 Pages, 1974/08
no abstracts in English
Akutsu, Hideo*; Mizuta, H.
PNC TN843 74-02, 122 Pages, 1974/02
None
Mizuta, H.; ;
PNC TN841 72-26, 57 Pages, 1972/07
A computer simulation code SASATSU(1), for nuclear materialflow and MUF has been programedfor analyzing the data of theATR and Rapsodie campaigns in thepresent facility. With thissimulation experience, the mater-ial flow characteristics in theFBR-line of the new facility isestimated.
