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Nakano, Masanao; Fujii, Tomoko; Nemoto, Masashi; Tobita, Keiji; Kono, Takahiko; Hosomi, Kenji; Nishimura, Shusaku; Matsubara, Natsumi; Maehara, Yushi; Narita, Ryosuke; et al.
JAEA-Review 2019-048, 165 Pages, 2020/03
JAEA-Review-2019-048.pdf:2.69MB
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2018 to March 2019. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc. (the trade name was changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016) in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and exceeded the normal range of fluctuation in the monitoring, were evaluated.
Nakano, Masanao; Fujita, Hiroki; Mizutani, Tomoko; Nemoto, Masashi; Tobita, Keiji; Kono, Takahiko; Hosomi, Kenji; Hokama, Tomonori; Nishimura, Tomohiro; Matsubara, Natsumi; et al.
JAEA-Review 2018-025, 171 Pages, 2019/02
JAEA-Review-2018-025.pdf:3.81MB
Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2016 to March 2017. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Electric Power Company Holdings, Inc. in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and were exceeded the normal range of fluctuation in the monitoring, were evaluated.
Mori, Eito; Yamamoto, Masahiko; Taguchi, Shigeo; Sato, Soichi; Kitao, Takahiko; Surugaya, Naoki
Nihon Hozen Gakkai Dai-11-Kai Gakujutsu Koenkai Yoshishu, p.132 - 138, 2014/07
The contamination of the radioactive material was observed on the filter casing surface of the glove box installed at the analytical laboratory in Tokai Reprocessing Plant. The cause of the contamination was investigated with visual inspection, penetrant testing and ultrasonic thickness measurement. It was found that a micro through-hole due to the corrosion of stainless-steel was generated in the glove box filter casing. The repair work of the filter casing was performed keeping the glove box negative pressure. The corrosion part of filter casing was replaced and newly fabricated casing was connected to the glove box with Tungsten Inert Gas welding method.
Ohgama, Kazuya; Ogino, Haruyuki*; Sato, Takahiko*; Suzuki, Ayako*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 53(7), p.509 - 513, 2011/07
no abstracts in English
Sato, Takahiko
JAEA-Technology 2007-020, 18 Pages, 2007/03
JAEA-Technology-2007-020.pdf:0.99MB
In the MOX fuels irradiated in FBR, the enhanced concentration of plutonium and americium together with fuel restructuring caused by the steep temperature gradient in the radial direction is observed around the central void. The atoms transport caused by thermal diffusion and the pore migration toward the pellet center due to evaporation-condensation is considered as Pu redistribution mechanism. Since the redistribution mechanism for Am is expected to be similar to that for Pu, assuming that their redistribution would be caused by the similar mechanism, we developed the redistribution model for Pu and Am. In order to verify the redistribution model for Pu and Am, the computed radial distribution of Pu and Am concentration was compared with the results of SXMA measurements for MOX fuels, of which initial Am concentration was 0.9 wt%, irradiation in JOYO. As a result, it was confirmed that the computed radial distribution of Pu and Am would be in good agreement with the observed one.
-induced changes in metallothionein expression and subcellular distribution of zinc in HepG2 cellsNagamine, Takeaki*; Kusakabe, Takahiko*; Takada, Hisashi*; Nakazato, Kyomi*; Sakai, Takuro; Oikawa, Masakazu*; Sato, Takahiro; Arakawa, Kazuo
Cytokine, 34(5-6), p.312 - 319, 2006/06
Times Cited Count：8 Percentile：16.51(Biochemistry & Molecular Biology)no abstracts in English
Nakano, Takashi*; Arakawa, Kazuo; Sakurai, Hideyuki*; Hasegawa, Masatoshi*; Yuasa, Kazuhisa*; Saito, Etsuko*; Takagi, Hitoshi*; Nagamine, Takeaki*; Kusakabe, Takahiko*; Takada, Hisashi*; et al.
International Journal of PIXE, 16(1&2), p.69 - 76, 2006/00
A new program was started out to create a new medical scientific field, which is consisting of radiation oncology and nuclear medicine, utilizing the advanced accelerator and ion beam technology. An in-air micro-PIXE analyzer system, which is among the most important technical basis of the program, was upgraded to improve accuracy of elemental mapping for samples having thickness variation in a scope of microbeam scanning. In the program, on the other hand, in order to approach important bio-medical problems on cancer, intracellular dynamics of the trace elements according to mechanism of development of diseases were studied using this system. This paper outlines this program and shows the system upgraded, and results of preliminary studied about the problems.
Taguchi, Shigeo; Surugaya, Naoki; Sato, Soichi; Kitao, Takahiko; Hina, Tetsuro; Toshiaki, Hiyama,
Dai-25-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.120 - 127, 2004/00
For the determination of Pu in the high active liquid waste (HALW), isotope dilution mass spectrometry (IDMS) has been applied to verification analysis at Tokai Reprocessing Plant. IDMS has been considered as the most reliable analytical technique for accountability measurement of Pu in spent fuel reprocessing plant. However, it takes quite long time for inspector to obtain an analytical result because inspection sample has to be transported to safeguards analytical laboratory for off-site analysis. In order to overcome this disadvantage, a rapid verification analysis of Pu in HALW by conventional spectrophotometer using Nd as an internal standard was proposed to achieve on-site verification measurements. In this method, Nd standard is intended to be provided by International Atomic Energy Agency (IAEA) so that an inspector can independently control it not only as an internal standard but also as an authentication purpose. The validation analysis was carried out by comparing with IDMS. It was found that the values of Pu concentration obtained by proposed method were in good agreement with those obtained by IDMS. Therefore the proposed method can be expected for the application to the verification analysis.
Surugaya, Naoki; Taguchi, Shigeo; Sato, Soichi; Kitao, Takahiko; Hina, Tetsuro; Hiyama, Toshiaki,
Proceedings of 45th INMM Annual Meeting, (112), p.33 - 34, 2004/00
A technique of measuring rapidly and correctly the concentration of Pu contained in the high radioactive liquid waste in a reprocessing plant has been developed. This method is based on spectrophotometry using Nd as an internal standard, and can be expected the application as measurement technology for the safeguards which has been utilizing the conventional method of isotope dilution mass spectrometry. This report describes the measurement principle and the result of the examination which used a real sample.
Surugaya, Naoki; Taguchi, Shigeo; Sato, Soichi; Hina, Tetsuro; Toshiaki, Hiyama,; Kitao, Takahiko
Proceedings of 45th INMM Annual Meeting, CD-ROM, 8p., 8 Pages, 2004/00
A rapid verification technique with conventional spectrophotometer has been developed to achieve on-site safeguards measurements in which neodymium as an internal standard was chosen to determine the plutonium concentration in high radioactive liquid waste.This method will provide the on-site analytical capabilities as it allows rapid and simple analyses at Tokai Reprocessing Plant.
Kitao, Takahiko; Sato, Soichi; Kuno, Takehiko; Keiji, Yamada,; Watahiki, Masaru; Kamata, Masayuki
JNC TN8410 2003-014, 29 Pages, 2003/11
JNC-TN8410-2003-014.pdf:1.82MB
The Agency requested the Tokai Reprocessing Plant(TRP) to confirm the applicability of three kinds of analytical procedure for Pu(VI) spectrophotometry in On-Site Analytical Laboratory (OSL) at Rokkasho, in order to obtain accurate plutonium(Pu) concentration in High Active Liquid Waste (HALW). Three analytical procedures, (1) Calibration method, (2) Nd internal standard method and (3) Reduction method, were tested. The measurement sample was prepared by adding the known amount of plutonium in the actual HALW after removing original Pu by solid extraction. We measured the Pu concentration in the sample by three methods and calculated the accuracy and precision. The results of each method are summarized as follows:(1) Calibration method Plutonium concentration calculated by the calibration method agreed with that by adjusted concentration. (2) Nd internal standard method Accurate results were obtained by this method. The error of pretreatment, especially dilution, has not influenced on the Pu measurements. (3) Reduction method The measured Pu concentrations were higher than those by adjusted. From the comparison with these results, the calibration method is the most simple and rapid in the three methods. Analysis time was within 1 hour including sample preparation. The detection limit, with the calibration method, was 1.3 mgPu/L in the actual HALW measurements.
Kitao, Takahiko; Jitsukata, Shu*; Sato, Soichi; Ikeda, Hisashi ; Atsushi, Ishibashi,; Surugaya, Naoki
SYMPOSIUM ON SAFEGUARDS AND NUCLEAR MATERIAL MANAGEMENT, 0 Pages, 2001/00
None
spectrometry in nitric acid mediaKitao, Takahiko; Nemoto, Hirokazu*; Shoji, Kazuhiro; Yamada, Keiji; Kurakata, Koichiro; Sato, Soichi
no journal, ,
no abstracts in English
Sato, Takahiko; Ozawa, Takayuki
no journal, ,
In the MOX fuels irradiated in FBR, the enhanced concentration of plutonium and americium together with fuel restructuring caused by the steep temperature gradient in the radial direction is observed around the central void. The atoms transport caused by thermal diffusion and the pore migration toward the pellet center due to evaporation-condensation is considered as Pu redistribution mechanism. Since the redistribution mechanism for Am is expected to be similar to that for Pu as the results of JOYO irradiation test, assuming that their redistribution would be caused by the similar mechanism, we developed the redistribution model for Pu and Am. The computed radial distribution of Pu and Am concentration was compared with the results of SXMA measurements for MOX fuels, irradiation in Uninstrumented Fuel Irradiation Subassembly Type-B of JOYO. As a result, it was confirmed that the computed radial distribution of Pu and Am would be in good agreement with the observed one.
Kusakabe, Takahiko*; Nakazato, Kyomi*; Takada, Hisashi*; Hisanaga, Etsuko*; Moon, H. D.*; Nakajima, Katsuyuki*; Suzuki, Keiji*; Oikawa, Masakazu*; Sato, Takahiro; Arakawa, Kazuo; et al.
no journal, ,
no abstracts in English
Sato, Takahiko; Ozawa, Takayuki
no journal, ,
no abstracts in English
Takizawa, Daichi*; Takagi, Hitoshi*; Makita, Chikako*; Nakajima, Yuka*; Saito, Etsuko*; Oyama, Tatsuya*; Ichikawa, Takeshi*; Kakizaki, Akira*; Sato, Ken*; Mori, Masatomo*; et al.
no journal, ,
no abstracts in English
Takada, Hisashi*; Kusakabe, Takahiko*; Nakazato, Kyomi*; Oikawa, Masakazu*; Sato, Takahiro; Kamiya, Tomihiro; Arakawa, Kazuo; Nagamine, Takeaki*
no journal, ,
no abstracts in English
Shimizu, Yasuo*; Dobashi, Kunio*; Kusakabe, Takahiko*; Nagamine, Takeaki*; Oikawa, Masakazu*; Sato, Takahiro; Haga, Junji*; Okubo, Takeru; Ishii, Yasuyuki; Kamiya, Tomihiro; et al.
no journal, ,
no abstracts in English
Kawano, Yasunori; Kondoh, Takashi; Ishikawa, Masao; Hatae, Takaki; Yatsuka, Eiichi; Imazawa, Ryota; Ogawa, Hiroaki; Sugie, Tatsuo; Takeuchi, Masaki; Sato, Kazuyoshi; et al.
no journal, ,
Recent progress in development of ITER diagnostic systems in Japan is presented as briefly shown below. (1) Microfission Chamber: A prototyping of vacuum feedthrough showed that the vacuum leak rate satisfies that of ITER requirement. (2) Thomson scattering (edge): A new method proposed for the measurement of anisotropic electron temperature was presented. (3) Poloidal Polarimeter: Measurement accuracy of the poloidal polarimeter was evaluated so that the accuracy of resultant current profile can satisfy the ITER measurement requirement. (4) Impurity influx monitor (divertor): By improvement of the design of equatorial port optics, expected detected light was 16 times increased in comparison with that of the previous design. (5) Divertor thermocouples (outer target): Investigation was started about the fixation method of the thermocouple on the side of divertor outer target. (6) Divertor IR thermography: Conceptual design activity was started for equatorial port optics.
