Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
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.
Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa; Nakagawa, Masayuki
JAERI 1348, 388 Pages, 2005/06
To realize fast and accurate Monte Carlo simulation of neutron and photon transport problems, two vectorized Monte Carlo codes MVP and GMVP have been developed at JAERI. MVP is based on the continuous energy model and GMVP is on the multigroup model. Compared with conventional scalar codes, these codes achieve higher computation speed by a factor of 10 or more on vector supercomputers. Both codes have sufficient functions for production use by adopting accurate physics model, geometry description capability and variance reduction techniques. The first version of the codes was released in 1994. They have been extensively improved and new functions have been implemented. The major improvements and new functions are (1) capability to treat the scattering model expressed with File 6 of the ENDF-6 format, (2) time-dependent tallies, (3) reaction rate calculation with the pointwise response function, (4) flexible source specification, etc. This report describes the physical model, geometry description method used in the codes, new functions and how to use them.
Otsuka, Naohiko; Aikawa, Masayuki*; Suda, Takuma*; Naito, Kenichi*; Korennov, S.*; Arai, Koji*; Noto, Hiroshi*; Onishi, Akira*; Kato, Kiyoshi*; Nakagawa, Tsuneo; et al.
AIP Conference Proceedings 769, p.561 - 564, 2005/05
A web-based search and plot system for nuclear reaction data has been developed, covering experimental data in EXFOR format and evaluated data in ENDF format. The system is implemented for Linux OS, with Perl and MySQL used for CGI scripts and the database manager, respectively. Two prototypes for experimental and evaluated data are presented.
Okumura, Keisuke; Nakakawa, Masayuki; Kaneko, Kunio*; *
JAERI-Conf 2000-018, p.31 - 41, 2001/01
Burnup calculation codes based on the conventional deterministic approach often encounter difficult problems because of the constraints on the geometry description, limit of approximation on the effective resonance cross-sections, failing of the diffusion approximation due to extremely strong anisotropic or heterogenity. They are, for example, the prediction of burn characteristics of plutonium spot, core design of ultra-small reactors, analysis of the sample material in an irradiation capsule of the research rector. To deal with these problems any time, a burn-up calculation code (MVP-BURN) was developed by using a continuous energy Monte Carlo code MVP. MVP-BURN was validated by comparison with the results of deterministic codes in the international benchmark problems, and by comparison with the measured values of the spent fuel composition irradiated in a commercial reactor.
Nakakawa, Masayuki
Robutsuri No Kenkyu, (51), p.47 - 51, 2000/12
no abstracts in English
Fujii, Yasunori*; Iwamoto, Akira; Fukahori, Tokio; Onuki, Toshihiko; Nakakawa, Masayuki; Hidaka, Hiroshi*; Oura, Yasutsugu*; M
ller, P.*
Nuclear Physics B, 573(1-2), p.377 - 401, 2000/05
Times Cited Count：191 Percentile：97.63(Physics, Particles & Fields)no abstracts in English
Nakagawa, Shigeaki; Shinozaki, Masayuki; Tachibana, Yukio; Kunitomi, Kazuhiko
JAERI-Tech 2000-038, p.39 - 0, 2000/03
JAERI-Tech-2000-038.pdf:1.86MB
no abstracts in English
Yamagishi, Hideshi; Ikeda, Yujiro; Ito, Hiroshi; Kakuta, Tsunemi; Nakakawa, Masayuki; Iwamura, Takamichi; Tabata, Hiroaki*; Urakami, Masao*
JAERI-Tech 2000-037, p.12 - 0, 2000/03
JAERI-Tech-2000-037.pdf:1.12MB
no abstracts in English
Kugo, Teruhiko; Tsuchihashi, Keiichiro*; Nakakawa, Masayuki; Ido, Masaru*
JAERI-Data/Code 2000-011, p.138 - 0, 2000/02
JAERI-Data-Code-2000-011.pdf:7.41MB
no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki
JAERI-Data/Code 2000-004, p.97 - 0, 2000/02
JAERI-Data-Code-2000-004.pdf:10.51MB
no abstracts in English
Okumura, Keisuke; Mori, Takamasa; Nakakawa, Masayuki; Kaneko, Kunio*
Journal of Nuclear Science and Technology, 37(2), p.128 - 138, 2000/02
no abstracts in English
Mori, Takamasa; Okumura, Keisuke; Nagaya, Yasunobu; Nakakawa, Masayuki
Mathematics and Computation, Reactor Physics and Environmental Analysis in Nuclear Applications, 2, p.987 - 996, 1999/09
no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki
Journal of Nuclear Science and Technology, 36(4), p.332 - 343, 1999/04
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Ueki, Kotaro*; Mori, Takamasa; Sakurai, Kiyoshi; Nakakawa, Masayuki; *
Nihon Genshiryoku Gakkai-Shi, 41(6), p.614 - 627, 1999/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Nagaya, Yasunobu; Nakakawa, Masayuki; Mori, Takamasa
Journal of Nuclear Science and Technology, 35(1), p.6 - 19, 1998/01
Times Cited Count：3 Percentile：31.9(Nuclear Science & Technology)no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki
Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.704 - 711, 1998/00
no abstracts in English
; Ushigusa, Kenkichi; Kikuchi, Mitsuru; Nagashima, Keisuke; Neyatani, Yuzuru; Miya, Naoyuki; ; Takahashi, Yoshikazu; Hayashi, Takumi; Kuriyama, Masaaki; et al.
Proceedings of 17th IEEE/NPSS Symposium Fusion Engineering (SOFE'97), 1, p.233 - 236, 1998/00
no abstracts in English
C-carbon fiber composite ceramics as plasma facing materials in nuclear fusion reactor, part 3; Heat resistance evaluation by electron beam irradiation and by in situ plasma discharge in JT-60*; Saido, Masahiro; Nakamura, Kazuyuki; Akiba, Masato; ; Dairaku, Masayuki; *; *; *; Goto, Yoshitaka*
Nihon Seramikkusu Kyokai Gakujutsu Rombunshi, 105(1228), p.1091 - 1098, 1997/12
Times Cited Count：1 Percentile：18.67(Materials Science, Ceramics)no abstracts in English
Kugo, Teruhiko; Nakakawa, Masayuki;
Journal of Nuclear Science and Technology, 34(8), p.760 - 770, 1997/08
Times Cited Count：2 Percentile：23.04(Nuclear Science & Technology)no abstracts in English
Nagashima, Keisuke; Kikuchi, Mitsuru; Kurita, Genichi; Ozeki, Takahisa; Aoyagi, Tetsuo; Ushigusa, Kenkichi; Neyatani, Yuzuru; Kubo, Hirotaka; Mori, Kensuke*; Nakagawa, Shoji*; et al.
Fusion Engineering and Design, 36(2-3), p.325 - 342, 1997/05
Times Cited Count：1 Percentile：14.48(Nuclear Science & Technology)no abstracts in English
