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Yamamoto, Kazami; Kinsho, Michikazu; Hayashi, Naoki; Saha, P. K.; Tamura, Fumihiko; Yamamoto, Masanobu; Tani, Norio; Takayanagi, Tomohiro; Kamiya, Junichiro; Shobuda, Yoshihiro; et al.
Journal of Nuclear Science and Technology, 59(9), p.1174 - 1205, 2022/09
Times Cited Count：6 Percentile：84.97(Nuclear Science & Technology)In the Japan Proton Accelerator Research Complex, the purpose of the 3 GeV rapid cycling synchrotron (RCS) is to accelerate a 1 MW, high-intensity proton beam. To achieve beam operation at a repetition rate of 25 Hz at high intensities, the RCS was elaborately designed. After starting the RCS operation, we carefully verified the validity of its design and made certain improvements to establish a reliable operation at higher power as possible. Consequently, we demonstrated beam operation at a high power, namely, 1 MW. We then summarized the design, actual performance, and improvements of the RCS to achieve a 1 MW beam.
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.
Kotake, Shoji*; Chikazawa, Yoshitaka; Takaya, Shigeru; Otaka, Masahiko; Kubo, Shigenobu; Arai, Masanobu; Kunogi, Kosuke; Ito, Takaya*; Yamaguchi, Akira*
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
A maintenance management required to prototype nuclear power reactors is proposed. Monitoring and control of sodium impurity and thermal transient are extremely important for sodium boundary maintenance for sodium-cooled fast reactors. At the fast stage of the prototype reactor Monju operation, degradation mechanism on the piping should be demonstrated based on operation experiences. Therefore inspection on a representative position for crack indication and pipe thickness is proposed. Due to less experience of SFR plants, early detection of boundary failure is considered. For a matured operation stage, when degradation mechanism is well demonstrated based on inspection data, inspection cycle could be extended. And for commercial reactors, maintenance without inspection will be established based on accumulated operation experiences including those of the prototype reactor Monju.
Arai, Masanobu; Kunogi, Kosuke; Aizawa, Kosuke; Chikazawa, Yoshitaka; Takaya, Shigeru; Kubo, Shigenobu; Kotake, Shoji*; Ito, Takaya*; Yamaguchi, Akira*
Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017) (CD-ROM), 6 Pages, 2017/04
Applications for maintenance program on piping support of prototype fast breeder reactor Monju are studied. Based on degradation mechanism, snubbers in Monju primary cooling system showed lifetime more than the plant lifetime of 30 years by experiments conservatively. For the first step during construction, visual inspection on accessible all supports could be available. In that visual inspection, mounting conditions and damages of all accessible supports could be monitored. One of major features of the Monju primary piping system is large thermal expansion due to large temperature difference between maintenance and operation conditions. Thanks to that large thermal expansion, integrity of the piping support could be monitored by measuring piping displacement. When technologies of piping displacement monitoring are matured in Monju, visual inspection on piping support could be shifted to piping displacement monitoring. At that stage, the visual inspection could be limited only on representative supports.
Mukai, Kazuo; Arai, Masanobu; Ito, Kazuhiro; Okawachi, Yasushi
Nihon Genshiryoku Gakkai-Shi ATOMO
, 56(9), p.554 - 560, 2014/09
no abstracts in English
Fujiwara, Kazushige*; Ito, Masanobu*; Sasanuma, Miwa*; Tanaka, Hideo*; Hirotani, Kiyoshi*; Onizawa, Kunio; Suzuki, Masahide; Amezawa, Hiroo*
Transactions of the 20th International Conference on Structural Mechanics in Reactor Technology (SMiRT-20) (CD-ROM), 8 Pages, 2009/08
Concerns over aged nuclear power stations are mounting in Japan today. However, there exists only a small number of experimental studies regarding the effect of radiation exposure to concrete. We have consequently conducted an irradiation test at JMTR on concrete specimens to confirm the effect of radiation exposure on the basic material properties of concrete. Irradiation temperature was kept lower than 65
C. The maximum fast neutron fluence reached 12
10
n/cm
(E
0.1 MeV), which is sufficiently exceeding total fast neutron fluence to be exposed to the concrete located at the exterior of a reactor pressure vessel in a typical BWR for 60-year operation. Compressive strength of the irradiated concrete specimens was roughly equivalent to that of concrete specimens cured for the same duration under the standard environment. By measuring chemically bound water content of irradiated specimens, no changes after irradiation were observed. It was confirmed that radiation exposure did not significantly affect the basic material properties of concrete within the range of radiation doses adopted in this study.
Akai, Masanobu; Ito, Nobuyuki*; Yamaguchi, Tetsuji; Tanaka, Tadao; Iida, Yoshihisa; Nakayama, Shinichi; Inagaki, Shingo*
JAERI-Tech 2004-058, 47 Pages, 2004/09
JAERI-Tech-2004-058.pdf:7.27MB
Geochemistry Research Equipment for TRU Waste Elements has been installed in Back-end Cycle Key Elements Research Facility (BECKY) of Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF). This equipment is designed to study geochemical behavior of TRU elements and other radionuclides contained in TRU waste (TRU waste elements) and to acquire data for safety assessments of radioactive wastes disposal. The equipment consists of anaerobic glove box systems, aerobic glove box systems equipped with built-in barrier performance testing apparatus, and analytical instruments. This report describes principles, structure, performance and safety designs of each component of the equipment, and results of research performed in the equipment.
Michino, Masanobu; Suzuki, Toshiaki; Aita, Tsuyoshi; Suto, Masayoshi; Saito, Takakazu; Kawahara, Hirotaka; Isozaki, Kazunori; Ito, Hideaki; Inoue, Setsunari; Aoki, Hiroshi; et al.
JNC TN9430 2004-001, 103 Pages, 2004/03
JNC-TN9430-2004-001.pdf:4.06MB
This report describes the results of the primary and secondary cooling system interlock test and the fuel handling system function test, which were done as a part of JOYO MK-3 function test. The items of the test are: (1) Primary and secondary cooling system interlock test (SKS-106,210) (2) Loss of electric power supply test (SKS-116) (3) In-vessel and ex-vessel automatic fuel transportation test (SKS-501,502) As the interlock of the primary and secondary cooling system was changed, the interlock test by the reactor scram and the loss of electric power supply was carried out. The function of the remote automatic fuel handling system was confirmed before the handling of the fuel for MK-3 core configuration. The results of the test satisfied the required performance, and it was confirmed that operation of the primary and secondary cooling system interlock and operation of the fuel handling system in JOYO MK-3 were normal.
Nakano, Hirotami*; Aono, Yoshinori*; Naito, Masanobu*; Kondo, Ryo*; Eda, Hiroshi*; Matsukawa, Makoto; Miura, Yushi
Denki Gakkai Rombunshi, D, 120D(11), p.1277 - 1282, 2000/11
no abstracts in English
Nakano, Hirotami*; Tanabe, Takeshi*; Naito, Masanobu*; Kubota, Yoshiki*; Morita, Tsuyoshi*; Kimura, Toyoaki; Matsukawa, Makoto; Miura, Yushi
Electrical Engineering in Japan, 131(4), p.1 - 10, 2000/04
Times Cited Count：8 Percentile：48.65(Engineering, Electrical & Electronic)no abstracts in English
*; Tanabe, Takeshi*; Naito, Masanobu*; Kubota, Yoshiki*; Morita, Tsuyoshi*; Kimura, Toyoaki; Matsukawa, Makoto; Miura, Yushi
Denki Gakkai Rombunshi, A, 119(3), p.279 - 285, 1999/03
no abstracts in English
crystalsMurakami, Go*; Abe, Kenichiro*; Ashida, Atsushi*; Wakita, Kazuki*; Watase, Seiji*; Izaki, Masanobu*; Oshima, Takeshi; Morishita, Norio; Ito, Hisayoshi
no journal, ,
no abstracts in English
Kato, Masashi*; Fukushima, Keisuke*; Kasuga, Masanobu*; Kito, Kosuke*; Ichimura, Masaya*; Kanechika, Masakazu*; Ishiguro, Osamu*; Kachi, Tetsu*; Oshima, Takeshi
no journal, ,
no abstracts in English
