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Journal Articles

Estimation of external dose for wild Japanese macaques captured in Fukushima prefecture; Decomposition of electron spin resonance spectrum

Mitsuyasu, Yusuke*; Oka, Toshitaka; Takahashi, Atsushi*; Kino, Yasushi*; Okutsu, Kenichi*; Sekine, Tsutomu*; Yamashita, Takuma*; Shimizu, Yoshinaka*; Chiba, Mirei*; Suzuki, Toshihiko*; et al.

Radiation Protection Dosimetry, 199(14), p.1620 - 1625, 2023/09

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

We have been conducting dose assessments for Japanese macaques captured in Fukushima to reveal radiobiological effects on the low-dose expose animals. To accurately determine the external exposure dose, it is desirable to examine the analysis of the CO$$_{2}^{-}$$ radical intensity. We examined ESR spectra of teeth of 10 macaques captured in Fukushima by two spectrum-decomposition algorithms.

Journal Articles

A Study on accuracy of analysis of the radiation-induced component in the ESR spectra of teeth

Mitsuyasu, Yusuke*; Oka, Toshitaka; Takahashi, Atsushi*; Kino, Yasushi*; Okutsu, Kenichi*; Sekine, Tsutomu*; Yamashita, Takuma*; Shimizu, Yoshinaka*; Chiba, Mirei*; Suzuki, Toshihiko*; et al.

KEK Proceedings 2022-2, p.120 - 125, 2022/11

We investigate the effect of sample's anisotropy and measurement condition to obtain the higher reproducibility for the shape of the ESR spectrum and the intensity of CO$$_{2}^{-}$$ radical.

Journal Articles

Detection limit of electron spin resonance for Japanese deciduous tooth enamel and density separation method for enamel-dentine separation

Oka, Toshitaka; Takahashi, Atsushi*; Koarai, Kazuma; Kino, Yasushi*; Sekine, Tsutomu*; Shimizu, Yoshinaka*; Chiba, Mirei*; Suzuki, Toshihiko*; Osaka, Ken*; Sasaki, Keiichi*; et al.

Journal of Radiation Research (Internet), 63(4), p.609 - 614, 2022/07

 Times Cited Count:1 Percentile:27.14(Biology)

Electron spin resonance (ESR) dosimetry is one of the most powerful tools for radiation dose reconstruction. The detection limit of this technique using human teeth is reported to be 56 mGy or 67 mGy; however, the absorbed dose of Fukushima residents after the Fukushima Daiichi Nuclear Power Plant (FNPP) accident was estimated to be lower than this detection limit. Our aim is to assess the absorbed radiation dose of children in Fukushima Prefecture after the accident; therefore, it is important to estimate the detection limit for their teeth. The detection limit for enamel of deciduous teeth of Japanese children separated by the mechanical method is estimated to be 115.0 mGy. The density separation method can effectively separate enamel from third molars of Japanese people. As we have collected thousands of teeth from children in Fukushima, the present technique may be useful to examine their external absorbed dose after the FNPP accident.

Journal Articles

Development of dose estimation method using wild animal teeth for low dose exposure

Mitsuyasu, Yusuke*; Oka, Toshitaka; Takahashi, Atsushi*; Koarai, Kazuma; Kino, Yasushi*; Okutsu, Kenichi*; Sekine, Tsutomu*; Yamashita, Takuma*; Shimizu, Yoshinaka*; Chiba, Mirei*; et al.

KEK Proceedings 2021-2, p.91 - 96, 2021/12

We examined whether the ESR dose estimation method could be applied to wild Japanese macaque. In this work, we investigated the enamel preparation protocol and the analytical method of the ESR spectra.

Journal Articles

Rapid analysis of $$^{90}$$Sr in cattle bone and tooth samples by inductively coupled plasma mass spectrometry

Koarai, Kazuma; Matsueda, Makoto; Aoki, Jo; Yanagisawa, Kayo*; Terashima, Motoki; Fujiwara, Kenso; Kino, Yasushi*; Oka, Toshitaka; Takahashi, Atsushi*; Suzuki, Toshihiko*; et al.

Journal of Analytical Atomic Spectrometry, 36(8), p.1678 - 1682, 2021/08

 Times Cited Count:5 Percentile:55.72(Chemistry, Analytical)

Rapid analysis of $$^{90}$$Sr in bone and tooth samples of cattle were achieved by an inductively coupled plasma mass spectrometry (ICP-MS) coupled with mass shift and solid phase extraction techniques. Limit of detection (LOD) in the ICP-MS measurement of 0.1 g samples was lower than that of the radioactivity measurement. Analytical time of the ICP-MS method was reduced from 20 days to 11 hours, compared with the radiometric method. Therefore, the ICP-MS method can be rapid and useful procedure of $$^{90}$$Sr in small bone and tooth samples derived from terrestrial animals.

Journal Articles

Radioactivity and radionuclides in deciduous teeth formed before the Fukushima-Daiichi Nuclear Power Plant accident

Takahashi, Atsushi*; Chiba, Mirei*; Tanahara, Akira*; Aida, Jun*; Shimizu, Yoshinaka*; Suzuki, Toshihiko*; Murakami, Shinobu*; Koarai, Kazuma; Ono, Takumi*; Oka, Toshitaka; et al.

Scientific Reports (Internet), 11(1), p.10355_1 - 10355_11, 2021/05

 Times Cited Count:6 Percentile:41.49(Multidisciplinary Sciences)

Journal Articles

External exposure dose estimation by electron spin resonance technique for wild Japanese macaque captured in Fukushima Prefecture

Oka, Toshitaka; Takahashi, Atsushi*; Koarai, Kazuma; Mitsuyasu, Yusuke*; Kino, Yasushi*; Sekine, Tsutomu*; Shimizu, Yoshinaka*; Chiba, Mirei*; Suzuki, Toshihiko*; Osaka, Ken*; et al.

Radiation Measurements, 134, p.106315_1 - 106315_4, 2020/06

 Times Cited Count:5 Percentile:53.85(Nuclear Science & Technology)

The relationship between the CO$$_{2}$$ radical intensity and the absorbed dose (dose response curve) of tooth enamel of Japanese macaque was observed by electron spin resonance and the detection limit of our system was estimated to be 33.5 mGy, which is comparable to the detection limit for human molar teeth. Using the dose response curve, external exposure dose for seven wild Japanese macaques captured in Fukushima prefecture were examined. The results suggest that the external exposure dose for the wild Japanese macaques were ranged between 45 mGy to 300 mGy.

Journal Articles

Demonstration of $$gamma$$-ray pipe-monitoring capabilities for real-time process monitoring safeguards applications in reprocessing facilities

Rodriguez, D.; Tanigawa, Masafumi; Nishimura, Kazuaki; Mukai, Yasunobu; Nakamura, Hironobu; Kurita, Tsutomu; Takamine, Jun; Suzuki, Satoshi*; Sekine, Megumi; Rossi, F.; et al.

Journal of Nuclear Science and Technology, 55(7), p.792 - 804, 2018/07

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Nuclear material in reprocessing facilities is safeguarded by random sample verification with additional continuous monitoring applied to solution masses and volume in important tanks to maintain continuity-of-knowledge of process operation. Measuring the unique $$gamma$$ rays of each solution as the material flows through pipes connecting all tanks and process apparatuses could potentially improve process monitoring by verifying the compositions in real time. We tested this $$gamma$$ ray pipe-monitoring method using plutonium-nitrate solution transferred between tanks at the PCDF-TRP. The $$gamma$$ rays were measured using a lanthanum-bromide detector with a list-mode data acquisition system to obtain both time and energy of $$gamma$$-ray. The analysis and results of this measurement demonstrate an ability to determine isotopic composition, process timing, flow rate, and volume of solution flowing through pipes, introducing a viable capability for process monitoring safeguards verification.

Journal Articles

Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security, 7; Measurement of DG from MOX and Pu liquid samples for quantification and monitoring

Mukai, Yasunobu; Ogawa, Tsuyoshi; Nakamura, Hironobu; Kurita, Tsutomu; Sekine, Megumi; Rodriguez, D.; Takamine, Jun; Koizumi, Mitsuo; Seya, Michio

Proceedings of INMM 57th Annual Meeting (Internet), 7 Pages, 2016/07

The development of Delayed Gamma-ray Spectroscopy (DGS) for analyzing the composition ratio of fissile nuclides ($$^{239}$$Pu, $$^{241}$$Pu, $$^{235}$$U) focused on the Delayed Gamma-ray having energy over 3 MeV has been performed for the development of active neutron non-destructive assay techniques. In PCDF, measurement tests of Delayed Gamma-ray using Pu solution and MOX powder samples to prove the DGS technique is planned to be performed in following 4 stages. (1) Measurements for Delayed Gamma-ray originated from spontaneous fission nuclide (Passive), (2) Measurements for the Delayed Gamma-ray with fast neutron (Active), (3) DGSI (DGS combined with self-interrogation) measurements (Passive), (4) Measurements for the Delayed Gamma-ray with thermal neutron (Active) In this paper, the plan of measurement tests for nuclear material samples with use of DGS is presented.

Journal Articles

The Project for grouting development for high level radioactive waste repository, 3; Study of allowable seepage water quantity by permiability test though contact face of buffer material blocks

Sekine, Ichiro*; Yamada, Tsutomu*; Sekiguchi, Takashi*; Fujita, Tomoo; Nakanishi, Tatsuro

Doboku Gakkai Heisei-23-Nendo Zenkoku Taikai Dai-66-Kai Nenji Gakujutsu Koenkai Koen Gaiyoshu (DVD-ROM), p.69 - 70, 2011/09

no abstracts in English

Journal Articles

The Project for grouting development for high level radioactive waste repository, 4; Development of superfine spherical silica grout

Yamada, Tsutomu*; Sekine, Ichiro*; Sekiguchi, Takashi*; Ishida, Hideaki*; Kishi, Hirokazu; Fukuoka, Naomi

Doboku Gakkai Heisei-22-Nendo Zenkoku Taikai Dai-65-Kai Nenji Gakujutsu Koenkai Koen Gaiyoshu (DVD-ROM), p.89 - 90, 2010/09

no abstracts in English

Journal Articles

Attempts to improve radiolytic stability of amidic extractants

Sugo, Yumi; Sasaki, Yuji; Kimura, Takaumi; Sekine, Tsutomu*

Proceedings of International Conference on Advanced Nuclear Fuel Cycles and Systems (Global 2007) (CD-ROM), p.1870 - 1873, 2007/09

A tridentate diamide, ${it N,N,N',N'}$-tetraoctyldiglycolamide (TODGA) is very useful for the recovery of actinide ions from spent nuclear fuel. Based on the mechanism of the radiolysis of TODGA in organic solution, an improvement of radiolytic stability of amidic extractants was attempted. The radiolytic degradation of TODGA was suppressed by the addition of appropriate compounds, due to reduction in the mole fraction of ${it n}$-dodecane. In addition, by using the solvents having low ionization potentials, TODGA could be protected from radiation. Because the charge transfer reaction in the primary process was inhibited. It was also confirmed that aromatic substituents in the molecule effectively improved the radiolytic stability.

Journal Articles

Influence of diluent on radiolysis of amides in organic solution

Sugo, Yumi; Izumi, Yoshinobu*; Yoshida, Yoichi*; Nishijima, Shigehiro*; Sasaki, Yuji; Kimura, Takaumi; Sekine, Tsutomu*; Kudo, Hiroshi*

Radiation Physics and Chemistry, 76(5), p.794 - 800, 2007/05

 Times Cited Count:78 Percentile:97.59(Chemistry, Physical)

The radiolytic behavior of ${it N,N,N',N'}$-tetraoctyldiglycolamide, ${it N,N'}$-dimethyl-${it N,N'}$-dioctyl-2-(3'-oxapentadecyl)malonamide, and ${it N,N}$-dioctylhexanamide in ${it n}$-dodecane was investigated by irradiation with $$gamma$$-rays and electron pulses. The results showed ${it n}$-dodecane has a sensitization effect on the radiolysis of these amides, owing mainly to a charge transfer from radical cations of ${it n}$-dodecane to the amide molecules in the primary process observed in pulse radiolysis.

Journal Articles

Radiolysis studies of amidic extractants for partitioning of HLW

Sugo, Yumi; Sasaki, Yuji; Kimura, Takaumi; Sekine, Tsutomu*

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 5 Pages, 2007/04

no abstracts in English

Journal Articles

Conversion of endohedral $$^{133}$$Xe-fullerene to endohedral $$^{133}$$Xe-fullerenol to be used in nuclear medicine

Watanabe, Satoshi; Ishioka, Noriko; Sekine, Tsutomu*; Kudo, Hiroshi*; Shimomura, Haruhiko*; Muramatsu, Hisakazu*; Kume, Tamikazu

Journal of Radioanalytical and Nuclear Chemistry, 266(3), p.499 - 502, 2005/11

 Times Cited Count:9 Percentile:53.19(Chemistry, Analytical)

no abstracts in English

Journal Articles

Radiolysis of TODGA and its effect on extraction of actinide ions

Sugo, Yumi; Sasaki, Yuji; Kimura, Takaumi; Sekine, Tsutomu*; Kudo, Hiroshi*

Proceedings of International Conference on Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) (CD-ROM), 4 Pages, 2005/10

no abstracts in English

Journal Articles

Distributions of uranium-series radionuclides in rock and migration rate of uranium at the Koongarra uranium deposit, Australia

Yanase, Nobuyuki; Sato, Tsutomu; ; Sekine, Keiichi

Radiochimica Acta, 82, p.319 - 325, 1998/00

no abstracts in English

Journal Articles

Selective extraction procedure and itsimportance in a natural analogue study; Case study at the Koongarra uranium deposit

Yanase, Nobuyuki; Sato, Tsutomu; Isobe, Hiroshi; Sekine, Keiichi

Hoshasei Haikibutsu Kenkyu, 2(1-2), p.121 - 135, 1996/02

no abstracts in English

JAEA Reports

Geochemical studies for geologic disposal of high-level radioactive waste; Research activities in Department of Environmental Safety Research, Japan Atomic Energy Research Institute

; Sato, Tsutomu; Nagano, Tetsushi; Yanase, Nobuyuki; Yamaguchi, Tetsuji; Isobe, Hiroshi; Onuki, Toshihiko; Sekine, Keiichi

JAERI-Review 95-011, 94 Pages, 1995/07

JAERI-Review-95-011.pdf:4.81MB

no abstracts in English

Journal Articles

Measurement of the thermal neutron cross section of the $$^{90}$$Sr(n,$$gamma$$)$$^{91}$$Sr reaction

Harada, Hideo*; Sekine, Toshiaki; ; ; Kobayashi, Katsutoshi; Otsuki, Tsutomu*; Kato, Toshio*

Journal of Nuclear Science and Technology, 31(3), p.173 - 179, 1994/03

 Times Cited Count:25 Percentile:87.25(Nuclear Science & Technology)

no abstracts in English

46 (Records 1-20 displayed on this page)