Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
-ray analysisKinoshita, Norikazu*; Noto, Takuma*; Nakajima, Hitoshi*; Kosako, Kazuaki*; Kato, Takahiro*; Kuroiwa, Yoichi*; Kurabe, Misako*; Sasaki, Yuki*; Torii, Kazuyuki*; Maeda, Makoto; et al.
Journal of Radioanalytical and Nuclear Chemistry, 332(2), p.479 - 486, 2023/02
Times Cited Count：2 Percentile：40.17(Chemistry, Analytical)Ohshima, Hiroyuki; Morishita, Masaki*; Aizawa, Kosuke; Ando, Masanori; Ashida, Takashi; Chikazawa, Yoshitaka; Doda, Norihiro; Enuma, Yasuhiro; Ezure, Toshiki; Fukano, Yoshitaka; et al.
Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3, 631 Pages, 2022/07
This book is a collection of the past experience of design, construction, and operation of two reactors, the latest knowledge and technology for SFR designs, and the future prospects of SFR development in Japan. It is intended to provide the perspective and the relevant knowledge to enable readers to become more familiar with SFR technology.
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.
Tsuji, Tomoyuki; Sugitsue, Noritake; Sato, Fuminori; Matsushima, Ryotatsu; Kataoka, Shoji; Okada, Shota; Sasaki, Toshiki; Inoue, Junya
Nihon Genshiryoku Gakkai-Shi ATOMO
, 62(11), p.658 - 663, 2020/11
no abstracts in English
Abe, Mitsushi*; Bae, S.*; Beer, G.*; Bunce, G.*; Choi, H.*; Choi, S.*; Chung, M.*; da Silva, W.*; Eidelman, S.*; Finger, M.*; et al.
Progress of Theoretical and Experimental Physics (Internet), 2019(5), p.053C02_1 - 053C02_22, 2019/05
Times Cited Count：167 Percentile：99.36(Physics, Multidisciplinary)This paper introduces a new approach to measure the muon magnetic moment anomaly 
and the muon electric dipole moment (EDM) 
at the J-PARC muon facility. The goal of our experiment is to measure 
and using an independent method with a factor of 10 lower muon momentum, and a factor of 20 smaller diameter storage-ring solenoid compared with previous and ongoing muon g-2 experiments with unprecedented quality of the storage magnetic field. Additional significant differences from the present experimental method include a factor of 1000 smaller transverse emittance of the muon beam (reaccelerated thermal muon beam), its efficient vertical injection into the solenoid, and tracking each decay positron from muon decay to obtain its momentum vector. The precision goal for is a statistical uncertainty of 450 parts per billion (ppb), similar to the present experimental uncertainty, and a systematic uncertainty less than 70 ppb. The goal for EDM is a sensitivity of 
e
cm.
Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*
Progress in Nuclear Science and Technology (Internet), 4, p.94 - 98, 2014/04
This paper evaluates the amount of activation of the secondary sodium in Direct Heat Exchanger (DHX) by neutrons leaked from the core, the radioactivity density, and the dose rate around the secondary sodium pipes in Direct Reactor Auxiliary Cooling System (DRACS) and confirms that the requirements in radioactivity free areas are satisfied by improving the exactness of calculation model with Monte Carlo Methodology.
Sakanaka, Shogo*; Akemoto, Mitsuo*; Aoto, Tomohiro*; Arakawa, Dai*; Asaoka, Seiji*; Enomoto, Atsushi*; Fukuda, Shigeki*; Furukawa, Kazuro*; Furuya, Takaaki*; Haga, Kaiichi*; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.2338 - 2340, 2010/05
Future synchrotron light source using a 5-GeV energy recovery linac (ERL) is under proposal by our Japanese collaboration team, and we are conducting R&D efforts for that. We are developing high-brightness DC photocathode guns, two types of cryomodules for both injector and main superconducting (SC) linacs, and 1.3 GHz high CW-power RF sources. We are also constructing the Compact ERL (cERL) for demonstrating the recirculation of low-emittance, high-current beams using above-mentioned critical technologies.
Sakakibara, Tetsuro; Aoyama, Yoshio; Yamaguchi, Hiromi; Sasaki, Naoto*; Nishikawa, Takeshi*; Murata, Minoru*; Park, J.*; Taniguchi, Shoji*; Fujita, Michiru*; Fukuda, Tomoyuki*; et al.
Proceedings of International Waste Management Symposium 2009 (WM '09) (CD-ROM), 15 Pages, 2009/03
The volume reduction treatment of solid waste system by ultra-high frequency induction furnace (UHFIF) was developed from FY2005 to FY2007. Basic data for melting performance were collected by non-radioactive experiments using the bench scale UHFIF with a crucible capacity of 10 liters. Based on the obtained data, engineering specifications were evaluated for a demonstration scale UHFIF with a crucible capacity of 30 liters. A new demonstration scale UHFIF was constructed and melting experiments of surrogate wastes were carried out by this furnace. It was confirmed that the demonstration scale UHFIF can melt ferrous metal, ceramics and aluminum all together and stabilize aluminum by oxidation to alumina. Density, chemical composition, and surface condition of the solidified substances were analyzed, and homogeneity of the solidified substances was confirmed. Melting behavior in the demonstration scale UHFIF was analyzed by computer simulation and simulation results agreed well with the experimental ones. From the design study for a full scale UHFIF with a crucible capacity of 100 liters, basic specifications were evaluated for the full scale UHFIF. Based on the obtained specification, melting behavior in the full scale UHFIF was analyzed by computer simulation.
Kuroha, Mitsuo; Takeda, Kunio; Iitsuka, Shoji; Sasaki, Shuichi; Okada, Toshio; Isozaki, Mikio; Daigo, Yoshimichi; Sato, Minoru
PNC TN941 81-49, 204 Pages, 1981/05
PNC type in-sodium hydrogen meters have been developed as leak detectors for LMFBR MONJU steam generators. In order to confirm the long-term reliability and the durability of the meters, the four meters were installed in three sodium loops at the O-arai Engineering Center, and they had been tested over a long time in flowing sodium. A period of the test was from oct. 1977 to Feb. 1980. They are called type II. The dynamic chamber of the vacuum system can separate from the static one, and be also connected with it using one flexible tube. Important findings from the test are; (1) The operating time of two meters exceeded 10,000 hours, and the total of all meters was about 35,000 hours. No trouble had been experienced in the sodium systems and the nickel membranes of them during the period, which had the good durability. Air leaks, however, occured three times in the two vacuum systems. (2) Any secular changes had hardly happened in the permeability of hydrogen through the nickel membrane and the relationship between ion pump current and hydrogen pressure. (3) The pumping speeds had decreased with increasing the amount of absorbed hydrogen. The decreasing rates differed among four ion pumps, and those of two pumps were considerably large at the beginning of absorbing hydrogen. (4) The calibration curves, which describe the relationship between hydrogen concentration in sodium and ion pump current, had changed with time. The largest cause was the decrement of the pumping speeds. (5) The UHV gauges were superior to the ion pumps from the point of the signal-to-noise ratio as the hydrogen sensor.
Sunakoda, Katsuaki*; Sasaki, Shoji*;
PNC TJ231 72-01, 30 Pages, 1972/10
With the purpose of developing a radiationproof hydraulic anti-vibration device (hereunder called AVD) for use in the primary loop of the Fast Breeder Reactor, we have manufactured a proto-type there of which was equipped with a metalic seal ring and a metalic 0-ring inits sealing mechanism. To check and investigate of its performance, we have carriedout a series of comprehensive tests including pressure test, vibrationtest, and static functional test with use of five types of hydraulicfluid for each of these tests (50, 100, 500, 1000, and 3000cSt.) Also, a leakage test and an fluid exchange test using 50cSt oilwere respectively performed. A heating test of this hydraulic AVD was practiced employing 500cSt hydraulic fluid. In the final process,a performance testof this AVD was undertaken employing radiationproof hydraulic fluids HIVAC F-5 and ARO-4 with and without 
Co-ray irradiation,and theresults of the test before and after were compared with each other. The viscosity of the hydraulic fluid has
Hashimoto, Kazuichi; Kawata, Tsuyoshi; Nagayama, Mineo; Komoto, Norio; Shoji, Kenji; Choki, Toshiyuki; Sasaki, Hirofumi; Kashimura, Takao; Kinoshita, Shigemi*
no journal, ,
no abstracts in English
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
Asaka, Takeo; Osaka, Masahiko; Donomae, Takako; Ichikawa, Shoichi; Sasaki, Shinji; Ishimi, Akihiro; Inoue, Toshihiko; Sekio, Yoshihiro; Miwa, Shuhei; Onishi, Takashi; et al.
no journal, ,
Activities on a system development for education and training of future experts in the nuclear field thorough experiments at PIE facilities are given. Basic concept of the system and acceptance-support apparatus are introduced.
Aoyama, Yoshio; Yamaguchi, Hiromi; Sakakibara, Tetsuro; Hanamoto, Yukio; Murata, Minoru*; Sasaki, Nao*; Nishikawa, Tsutomu*; Taniguchi, Shoji*; Shimazaki, Shinichi*; Park, J.*; et al.
no journal, ,
no abstracts in English
Sasaki, Shoji*; Kanemaru, Ryota*; Matsuura, Hirotaka*; Ihara, Toshihiro*; Seko, Noriaki
no journal, ,
no abstracts in English
Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*
no journal, ,
no abstracts in English
Miyamoto, Yasuaki; Yamaguchi, Hiromi; Aoyama, Yoshio; Nishikawa, Tsutomu*; Sasaki, Nao*; Murata, Minoru*; Taniguchi, Shoji*; Fujita, Michiru*; Suzuki, Hiroshi*
no journal, ,
no abstracts in English
Yamaguchi, Hiromi; Miyamoto, Yasuaki; Aoyama, Yoshio; Nishikawa, Tsutomu*; Sasaki, Nao*; Murata, Minoru*; Taniguchi, Shoji*; Fujita, Michiru*; Suzuki, Hiroshi*
no journal, ,
no abstracts in English
Yamaguchi, Hiromi; Miyamoto, Yasuaki; Sakakibara, Tetsuro; Hanamoto, Yukio; Aoyama, Yoshio; Sasaki, Nao*; Nishikawa, Tsutomu*; Murata, Minoru*; Muroi, Masayuki*; Park, J.*; et al.
no journal, ,
no abstracts in English
