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Sano, Yuichi; Sakamoto, Atsushi; Miyazaki, Yasunori; Watanabe, So; Morita, Keisuke; Emori, Tatsuya; Ban, Yasutoshi; Arai, Tsuyoshi*; Nakatani, Kiyoharu*; Matsuura, Haruaki*; et al.
Proceedings of International Conference on Nuclear Fuel Cycle; Sustainable Energy Beyond the Pandemic (GLOBAL 2022) (Internet), 4 Pages, 2022/07
We developed a hybrid MA(III) recovery process combining MA(III)+Ln(III) co-recovery flowsheet by solvent extraction with TBP and MA(III)/Ln(III) separation flowsheet by simulated moving bed chromatography using HONTA impregnated adsorbents with large particle size porous silica support.
Uto, Hiroyasu; Takase, Haruhiko; Sakamoto, Yoshiteru; Tobita, Kenji; Mori, Kazuo; Kudo, Tatsuya; Someya, Yoji; Asakura, Nobuyuki; Hoshino, Kazuo; Nakamura, Makoto; et al.
Fusion Engineering and Design, 103, p.93 - 97, 2016/02
Times Cited Count：8 Percentile：60.26(Nuclear Science & Technology)Conceptual design of in-vessel component including conducting shell has been investigated in Broader Approach (BA) DEMO design activities, in order to propose feasible DEMO reactor from plasma vertical stability and engineering viewpoint. The conducting shell for the plasma vertical stability will be incorporated behind blanket module, while the location must be close to the plasma surface as possible for the plasma stabilization. We evaluated dependence of the plasma vertical stability on the conducing shell parameters by using a 3-dimensional eddy current analysis code (EDDYCAL). The calculation results showed that the conducting shell requires more than 0.01 m thickness of Cu-alloy on DEMO. On the other hand, the electromagnetic force at the plasma disruption is a few times larger than no conducting shell case because of larger eddy current on conducting shell. The engineering design issues of in-vessel components for plasma vertical stability are presented.
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.
Sato, Shoichi*; Ichimura, Makoto*; Yamaguchi, Yusuke*; Katano, Makoto*; Imai, Yasutaka*; Murakami, Tatsuya*; Miyake, Yuichiro*; Yokoyama, Takuro*; Moriyama, Shinichi; Kobayashi, Takayuki; et al.
Plasma and Fusion Research (Internet), 5, p.S2067_1 - S2067_4, 2010/12
Ion cyclotron emissions (ICEs) due to deuterium-deuterium fusion-product (FP) ions on JT-60U are studied. ICE due to H-ions is identified from the difference of the toroidal wave number of 2nd ICE(D). The parameter dependence for the appearance of ICE(H) is investigated from the experimental conditions and also is studied by using "Escape Particle Orbit analysis Code (EPOC)".
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.
Ichimura, Makoto*; Yamaguchi, Yusuke*; Sato, Shoichi*; Katano, Makoto*; Ouchi, Toshiaki*; Muro, Taishi*; Sekihara, Yusuke*; Murakami, Tatsuya*; Moriyama, Shinichi; Kobayashi, Takayuki; et al.
no journal, ,
Fluctuations in the ion cyclotron range of frequency are investigated both on GAMMA 10 and JT-60U. Ion cyclotron emissions (ICEs) due to deuterium-deuterium fusion-product (FP) ions on JT-60U are described. ICE due to H-ions is newly identified. ICE(T) with lower frequency has larger wave numbers than ICE (
He) in the same discharge. The excitation of slow Alfv
n waves is elucidated for the first time as the mechanism for ICE due to T-ions. The anisotropy of T-ions at the outer plasma edge is evaluated by using Escape Particle Orbit analysis Code (EPOC).
Sato, Shoichi*; Ichimura, Makoto*; Yamaguchi, Yusuke*; Katano, Makoto*; Imai, Yasutaka*; Murakami, Tatsuya*; Miyake, Yuichiro*; Yokoyama, Takuro*; Moriyama, Shinichi; Kobayashi, Takayuki; et al.
no journal, ,
Ion cyclotron emissions (ICEs) due to deuterium-deuterium fusion-product (FP) ions on JT-60U are studied. ICE due to H-ions is identified from the difference of the toroidal wave number of 2nd ICE(D). The parameter dependence for the appearance of ICE(H) is investigated from the experimental conditions and also is studied by using "Escape Particle Orbit analysis Code (EPOC)".
screening of target kinases of AtATRSakamoto, Ayako; Nemoto, Keiichiro*; Seki, Motoaki*; Shinozaki, Kazuo*; Sawasaki, Tatsuya*
no journal, ,
Takase, Haruhiko; Tobita, Kenji; Sakamoto, Yoshiteru; Uto, Hiroyasu; Mori, Kazuo; Kudo, Tatsuya
no journal, ,
Analysis of plasma position control is one of important issues for design of DEMO reactor on Broader Approach (BA). Especially, plasma performance, blanket design and maintenance scheme influence the plasma position control mutually. Therefore, we made a numerical simulation code that consists of plasma equilibrium analysis, eddy current analysis and plasma motion analysis. Since we analyzed several cases of design using this numerical simulation code, the results will be shown.
Takase, Haruhiko; Uto, Hiroyasu; Sakamoto, Yoshiteru; Mori, Kazuo; Kudo, Tatsuya; Tobita, Kenji
no journal, ,
Pre-conceptual design of DEMO reactor has been preceded under collaboration Japan and Europe (Broader Approach activities (BA)). In the case of DEMO reactor, it is important for design of plasma position control to take into account the actual shape of vacuum vessel and in-vessel components precisely since the design condition of DEMO reactor is different from current tokamak devices and ITER (for example, installation of maintenance ports). To consider the DEMO design condition, the numerical simulation that consists of three modules has been developed. As results, (1) The time constants of eddy current in the breeding blankets are less than 10ms and there is no influence to passive stabilization effect. (2) The stabilization effect of conducting components decreases by considering installation of vertical maintenance port. The adoption of vertical port is related to the choice of the maintenance scenario.
Motoshima, Takayuki*; Usui, Tatsuya*; Sakamoto, Atsushi*; Niunoya, Sumio*; Ishida, Tomoko*; Miura, Norihiko*; Nakayama, Masashi; Ono, Hirokazu
no journal, ,
Japan Atomic Energy Agency is conducting the in-situ experiment for verification of performance of engineered barrier system in Horonobe Underground Research Laboratory. The purpose of this paper is reporting the mix design of high-workable low-alkaline plug concrete. This paper also reports the thermal stress analysis of plug concrete and results of in-situ thermal measurements.
Uto, Hiroyasu; Takase, Haruhiko; Sakamoto, Yoshiteru; Tobita, Kenji; Hiwatari, Ryoji; Mori, Kazuo; Kudo, Tatsuya; Someya, Yoji; Asakura, Nobuyuki
no journal, ,
This presentation describes conceptual design of in-vessel component including conducting shell in DEMO design activities, in order to propose feasible DEMO reactor from plasma vertical stability and engineering viewpoint. The conducting shell design for plasma vertical stability was clarified from the plasma vertical stability analysis, and a conceptual design divided in the toroidal direction for the blanket remote maintenance was proposed. We evaluated dependence of the plasma vertical stability on the conducing shell parameters and electromagnetic force at plasma disruption by using a numerical simulation code (EDDYCAL) with actual shape and position of the vacuum vessel and in-vessel components. The calculation results showed that the double-loop shell has the most effect on plasma vertical stability. On the other hand, while the electromagnetic force at the plasma disruption is a few times larger than no conducting shell case because of larger eddy current on conducting shell.
Takase, Haruhiko; Uto, Hiroyasu; Sakamoto, Yoshiteru; Mori, Kazuo; Kudo, Tatsuya; Hiwatari, Ryoji; Tobita, Kenji
no journal, ,
Plasma position control for DEMO reactor has been studied using numerical simulation, which consists of plasma equilibrium, eddy current and active feedback control analyses. The stabilization effect of in-vessel components, the influence on the magnetic detector and the power of active feedback control coils are evaluated. Especially, the influence on plasma position control by installation of the breeding blanket modules is shown in this paper.
on the properties and structure of iron phosphate glassNomura, Akira*; Kitamura, Naoto*; Saito, Akira*; Sakamoto, Tatsuaki*; Takebe, Hiromichi*; Kobayashi, Hidekazu; Amamoto, Ippei; Nakamura, Hiroki*; Mitamura, Naoki*; Tsuzuki, Tatsuya*
no journal, ,
no abstracts in English
Tanno, Takashi; Yano, Yasuhide; Tsukada, Tatsuya*; Sakamoto, Kan*; Yamashita, Shinichiro
no journal, ,
no abstracts in English
Tanno, Takashi; Yano, Yasuhide; Tsukada, Tatsuya*; Sakamoto, Kan*; Yamashita, Shinichiro
no journal, ,
FeCrAl-ODS stainless steel cladding with Al has been developed to improve oxidation resistance for accident tolerant fuel of LWRs. The strength of weld part may decrease due to growth of fine oxide particles, when the weld method with fusion is used for the end cap joining of FeCrAl-ODS stainless steel. For FeCrAl-ODS stainless steel cladding for fast reactors, the pressurization resistance welding (PRW) mood which is solid-state welding has been developed by an atomic organization. It is reported the results of joining tests that applied the PRW method about a FeCrAl-ODS stainless steel.
