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Wada, Yuki*; Kamogawa, Masashi*; Kubo, Mamoru*; Enoto, Teruaki*; Hayashi, Shugo*; Sawano, Tatsuya*; Yonetoku, Daisuke*; Tsuchiya, Harufumi
Journal of Geophysical Research; Atmospheres, 128(21), p.e2023JD039354_1 - e2023JD039354_20, 2023/11
Times Cited Count：0Yamamoto, 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.
Shibata, Takanori*; Hirano, Koichiro; Hirane, Tatsuya*; Shinto, Katsuhiro; Hayashi, Naoki; Oguri, Hidetomo
Proceedings of 18th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.417 - 421, 2021/10
In J-PARC linac, the operation of an rf-driven high-intensity H
ion source was initiated in 2014. For plasma ignition, the 2-MHz rf amplifier outputs the power of several tens kW. However the rf amplifier for the ion source and those for the accelerating cavities have not been synchronized. As a result, the wave hights in the beam waveforms were different in shot by shot. Therefore, we have developed an synchronization system between the rf system for the ion source and those for the cavity systems and succeeded the same wave hights in the waveforms.
Takahashi, Hiroki; Hayashi, Naoki; Nishiyama, Koichi*; Suzuki, Takahiro*; Ishiyama, Tatsuya*
Proceedings of 16th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.271 - 274, 2019/07
In the event of an abnormal situation, a machine protection system (MPS) that immediately inhibits the beam is indispensable to minimize the damage and the radioactivation by beam loss. The existing MPS was developed during the construction period of the J-PARC. Then, the system has been working stably for more than ten years. On the other hand, since there are many MPS modules that have been used from the beginning of J-PARC operation, it is important to systematically proceed with updating (replacement) of modules as a measure against aging of MPS. However, the main components of the existing MPS module have been discontinued. Therefore, it is indispensable to redesign the MPS modules in consideration of improvement such as the compatibility with existing modules and the miniaturization. In this paper, the development status of the new module and the update plan of MPS for Linac and RCS are detailed.
Sawabe, Yuki*; Ishiyama, Tatsuya; Takahashi, Daisuke; Kato, Yuko; Suzuki, Takahiro*; Hirano, Koichiro; Takei, Hayanori; Meigo, Shinichiro; Kikuzawa, Nobuhiro; Hayashi, Naoki
Proceedings of 13th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.647 - 651, 2016/11
In the J-PARC, a 3 MeV linac has been developed for the tests of beam scraper irradiation and charge exchange by high-power laser. To accomplish tests efficiently and safely, the control system for 3 MeV was designed and developed, and this system consists of four subsystems, personal protection system, machine protection system, timing system, and remote control system using the EPICS. In this paper, the details of control system for a 3 MeV linac are presented.
Sawabe, Yuki; Maruta, Tomofumi*; Liu, Y.*; Miura, Akihiko; Miyao, Tomoaki*; Ishiyama, Tatsuya; Kikuzawa, Nobuhiro; Hayashi, Naoki
Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.1202 - 1205, 2015/09
no abstracts in English
Yoshimoto, Masahiro; Saha, P. K.; Yamazaki, Yoshio; Kawase, Masato; Saeki, Riuji; Hayashi, Naoki; Yamamoto, Kazami; Hotchi, Hideaki; Ishiyama, Tatsuya; Kinsho, Michikazu; et al.
Journal of Physics; Conference Series, 417, p.012073_1 - 012073_6, 2013/03
Times Cited Count：4 Percentile：75.73(Materials Science, Coatings & Films)The HBC foil are installed in the J-PARC RCS for the charge-exchange H
beam injection. In order to examine the characteristics of the HBC foils, beam studies for the HBC foil were carried out from the viewpoint of foil's life time and the beam survival rate due to foils. According to the compromise between charge-exchange efficiency and foil scattering beam loss, we optimized the foils thickness for user operation. The long-term observation during the user operation as well as the HBC foil endurance test for its life time evaluation was carried out. Even after one year was operation, there was no deterioration of the stripping foil.
Matsubara, Masaaki*; Hayashi, Tatsuya*; Suzuki, Masato*; Shiraishi, Taisuke*; Sakamoto, Kenji*; Wakai, Takashi
Nihon Kikai Gakkai M&M 2011 Zairyo Rikigaku Kanfarensu Koen Rombunshu (CD-ROM), 2 Pages, 2011/07
In this study, we investigated the influence of two or more flaws on the collapse strength of austenitic stainless steel piping to improve the safety of a nuclear power plant. The multiple flaws may be more often than single flaw. Therefore, it is important to evaluate the collapse strength of the piping with multiple flaws. Piping with a single flaw and multiple flaws were used in the examination. Collapse strength of the piping is verified under the combination condition of tension and bending. It aims to model from multiple flaws to the single flaw for simplification of the. As a result, (1) It is possible to evaluate the collapse strength by identifying the multiple flaws as the single flaw conservatively. (2) On each load condition, the parallel notches on piping can be accounted to be the single notch.
Morita, Takami*; Niwa, Kentaro*; Fujimoto, Ken*; Kasai, Hiromi*; Yamada, Haruya*; Nishiuchi, Ko*; Sakamoto, Tatsuya*; Godo, Waichiro*; Taino, Seiya*; Hayashi, Yoshihiro*; et al.
Science of the Total Environment, 408(16), p.3443 - 3447, 2010/06
Times Cited Count：13 Percentile：33(Environmental Sciences)Iodine-131 (
I) was detected in brown algae collected off the Japanese coast. The maximum measured specific activity of I in brown algae was 0.37
0.010 Bq/kg-wet. Cesium-137 (
Cs) was also detected in all brown algal samples used in this study. There was no correlation between specific activities of I and Cs in these seaweeds. Low specific activity and minimal variability of Cs in brown algae indicated that past nuclear weapon tests were the source of Cs. Although nuclear power facilities are known to be pollution sources of I, there was no relationship between the sites where I was detected and the locations of nuclear power facilities. Most of the sites where I was detected were near big cities with large populations. On the basis of the results, we suggest that the likely pollution source of I, detected in brown seaweeds, is not nuclear power facilities, but nuclear medicine procedures.
Yoshimoto, Masahiro; Yamazaki, Yoshio; Hayashi, Naoki; Yamamoto, Kazami; Saeki, Riuji; Hotchi, Hideaki; Saha, P. K.; Harada, Hiroyuki; Kawase, Masato; Ishiyama, Tatsuya; et al.
Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.3927 - 3929, 2010/05
The (
)ybrid type thick (
)oron-doped (
)arbon (HBC) stripping foils are installed and used for the beam injection at the 3GeV RCS (Rapid Cycling Synchrotron) in J-PARC (Japan Proton Accelerator Research Complex). Up to now, the performance deterioration of the stripping foils can not be seen after the long beam irradiation for the 120kW user operation and 300kW high power beam demonstration at the RCS. In order to examine the characteristic of the HBC foils, various beam studies were carried out. The beam-irradiated spot at the foil was measured by scanning the foil setting position, the charge exchange efficiency was evaluated with various thickness foils, and the effect of the SiC fibers supporting the foil mounting was checked with different mounting foils. Beam study results obtained with using the HBC foils will be presented. In addition, the trends of outgas from the stripping foils and the deformations of the foils during the beam irradiation will be reported.
Naganuma, Masayuki; Aida, Tatsuya*; Hayashi, Hideyuki
JAEA-Research 2006-087, 72 Pages, 2007/02
JAEA-Research-2006-087.pdf:4.5MB
In the core and fuel design of sodium-cooled MOX fuel FR of FS, core designs with pellet fuel were mainly evaluated. However, vibro-packed fuel and sphere-pac fuel are also considered one of the candidates. Besides, the design must be affected by difference of the fuel behavior, however, the influence had not yet been evaluated adequately. Thus, authors examined the fuel thermal design model and evaluated the influences to the core and fuel design quantitatively. As a result, in the fuel thermal design model, selection of restructuring conditions was found to be important. Proper values were evaluated from the viewpoint of fitting PIE results. In applying this model, limitation of the stationary LHR was reduced to 390 W/cm. For FS phase-II reference cores, though it is required to modify specifications due to the decrease of LHR, the influence to nuclear performance is found to be benign. Therefore, the design that meets the requirements and targets of FS is possible for those fuels.
Oki, Shigeo; Sugino, Kazuteru; Ogawa, Takashi; Aida, Tatsuya*; Hayashi, Hideyuki
JAEA-Research 2006-077, 86 Pages, 2006/11
JAEA-Research-2006-077.pdf:6.34MB
Core and fuel design study of 
was performed. The reference specification of the large-scale (1,500 MWe) and the middle-scale (750 MWe) cores were proposed as a final result of 
. Since the local conversion ratio of any of the core points is made close to unity with single Pu enrichment, it is possible to minimize the necessary coolant flow rate for the core region and then, accept high reactor outlet temperature of 550
C. By the rationalization of hot spot factors, the coolant flow distribution design can be optimized to 5 regions for the large-scale core and 8 regions for the middle-scale core, respectively. It was also confirmed that the core specification met the criteria of fuel-assembly integrity, as well as those of shielding design. For further improvement on the reactor outlet temperature condition, the reduction of the maximum cladding inner-wall temperature was investigated with the reflection of the actual control rod insertion depth and the rationalization of the excess-reactivity uncertainty. An alternative core design was investigated by adopting the PNC-FMS steel as the cladding material instead of the ODS steel. As a result of the investigation of extending the control rod lifetime, three-cycle lifetime (which is the same as fuel assemblies) could be possible by means of the reductions in 
B enrichment and B
C pellet diameter.
Naganuma, Masayuki; Aida, Tatsuya*; Hayashi, Hideyuki
JAEA-Research 2006-063, 97 Pages, 2006/09
JAEA-Research-2006-063.pdf:9.19MB
In the Feasibility Study in Japan (FS), transmutation technology of LLFP using commercial fast reactors has been studied to reduce the environmental burden. In this report, loading type of LLFP target assembly, transmutation performances of FS designed cores and capability of transmutation core with high SF (transmutation / production ratio) are studied. Design studies for two loading types cores (in-core and ex-core loading type) were conducted for comparison. The in-core loading type core was found to decrease LLFP inventories significantly, thus, that was selected as the reference of FS. For FS phase-II designed cores, LLFP transmutation performances were evaluated. Every core was confirmed to have the capability to attain SF 
1.0. Then, we conducted sensitivity evaluations of design conditions to SF for transmutation core with high SF. Since sensitivities of every condition were found to be small, we concluded that large SF may be impossible for the commercial reactors.
Ogawa, Takashi; Sato, Isamu; Naganuma, Masayuki; Aida, Tatsuya*; Sugino, Kazuteru; Hayashi, Hideyuki
JAEA-Research 2006-061, 54 Pages, 2006/09
JAEA-Research-2006-061.pdf:3.86MB
Sodium cooled fast reactor with mixed oxide fueled core is one of the promising candidates in "Feasibility Study on Commercialized Fast Reactor Cycle System" in Japan. The results of the study on the reactor core and fuel design in the JFY2005 are reported. (1)Design studies of high internal conversion (HIC) type core: (i)Influence of TRU composition variation on the HIC type core and fuel designs was evaluated. (ii)In adopting PNC-FMS steel as alternative cladding material of ODS steel, influence to the reactor core and fuel design was evaluated for the large-scale HIC type core. (iii)Shielding property of the large-scale HIC type core was evaluated. (iv)Some measures to extend the lifetime of control rod were studied for the large-scale HIC type core. (2)Design study on high breeding performance: The core design corresponding to a requirement of high breeding performance was studied based on the large-scale compact type core designed in the JFY2004.
(
), a novel hypernodulation mutant of 
affected in vascular tissue organization and floral inductionKira, Erika*; Tateno, Kumiko*; Miura, Kinichiro*; Haga, Tatsuya*; Hayashi, Masaki*; Harada, Kyuya*; Sato, Shusei*; Tabata, Satoshi*; Shikazono, Naoya; Tanaka, Atsushi; et al.
Plant Journal, 44(3), p.505 - 515, 2005/11
Times Cited Count：90 Percentile：86.71(Plant Sciences)no abstracts in English
Yamauchi, Tatsuya; Iwai, Hiroki; Hayashi, Kenta; Tsuchida, Daisuke
no journal, ,
no abstracts in English
