KINDAI UNIVERSITY


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YAMANISHI Hirokuni

Profile

FacultyAtomic Energy Research Institute
PositionDirector
Degree
Commentator Guidehttps://www.kindai.ac.jp/meikan/259-yamanishi-hirokuni.html
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Mail
Last Updated :2020/09/30

Education and Career

Education

  •  - 1991 , Nagoya University
  •  - 1991 , Nagoya University, Graduate School, Division of Engineering
  •  - 1986 , Nagoya University, School of Engineering
  •  - 1986 , Nagoya University, Faculty of Engineering

Academic & Professional Experience

  •   2019 04 ,  - 現在, Director, Atomic Energy Research Institute, Kindai university
  •   2013 04 ,  - 現在, Professor, Atomic Energy Research Institute, Kindai university
  •   2011 04 ,  - 2013 03 , Associate professor, Atomic Energy Research Institute, Kindai university
  •   2006 01 ,  - 2011 03 , Safety and Environmental Research Center, National Institute for Fusion Science
  •   1991 04 ,  - 2005 12 , Safety and Environmental Research Center, National Institute for Fusion Science
  •   2006 , - Associate Professor, Safty and Environmental
  •   1991 ,  - 2005 , Research Associate, Safty and Environmental
  • Science
  • Research Center, National Institute for Fusion
  • Science
  • Research Center, National Institute for Fusion

Research Activities

Research Areas

  • Humanities & social sciences, Educational technology
  • Energy, Nuclear engineering
  • Environmental science/Agricultural science, Environmental effects of chemicals
  • Environmental science/Agricultural science, Environmental effects of radiation

Research Interests

  • Education for radiation use, Radiation monitoring, Natural radiation, Health Physics

Published Papers

  • A Practical Support Study Headed to Reconstruction and Its Volume Reduction of Radiation-Exposed Biomass using by Biocoke Technology, 大橋憲, 笹内謙一, 水野諭, 井田民男, 山西弘城, スマートプロセス学会誌, スマートプロセス学会誌, 5(3), 185‐190, May 20 2016
  • 電気泳動法によるセシウム汚染土壌の再生技術, 井原辰彦, 北岡 賢, 田中尚道, 山西弘城, 伊藤哲夫, 野間 宏, 放射性物質対策技術 除去・モニタリング・装置・システム開発, 放射性物質対策技術 除去・モニタリング・装置・システム開発, 2015, 145 - 154, 2015 , Refereed
  • Migration of Radioactive Cesium to Water from Grass and Fallen Leaves, H. Yamanishi, M. Inagaki, G. Wakabayashi, S. Hohara, T. Itoh, M. Furukawa, “Radiological Issues for Fukushima’s Revitalized Future”, (T. Takahashi editor), “Radiological Issues for Fukushima’s Revitalized Future”, (T. Takahashi editor), 47 - 55, 2015 , Refereed
  • Measurements for a Contamination Control of a ^<223>Ra Medicament, HOHARA Sin-ya, HOSONO Makoto, INAGAKI Masayo, IM Sung-Woon, MORIMOTO Hideo, HANAOKA Kohei, SAKAGUCHI Kenta, YAMANISHI Hirokuni, ITOH Tetsuo, RADIOISOTOPES, RADIOISOTOPES, 62(9), 659 - 665, Sep. 15 2013
    Summary:In recent years, attention has been focused on radionuclide therapy with &alpha; emission nuclides. Research and clinical tests of pharmaceuticals including <sup>223</sup>Ra, which has short half-life and a number of &alpha; & &beta; decays with its decay family, started in Japan in this year. Despite the fact that research on pharmaceuticals including <sup>223</sup>Ra is continuing, methods and knowledge of <sup>223</sup>Ra radiation controls have not been researched.<br>Contamination controls of radioactive pharmaceuticals in clinical sites are very important because of radiation protection, and research on <sup>223</sup>Ra-contamination controls should be performed as soon as possible before any medical application becomes licensed.<br>In this work, we performed demonstration experiments of <sup>223</sup>Ra-contamination with commonly-used survey meters. The results of experiments show that a Geiger-Muller type survey meter(TGS-133:Hitachi Aloka Medical) is effective to find <sup>223</sup>Ra-contamination, but an NaI(Tl) scintillation type survey meter(TCS-161:Hitachi Aloka Medical) should be used carefully due to the measurement limit in a <sup>223</sup>Ra-contamination survey.
  • Support Activities for Radiation Protection and Measurements in Kawamata-machi, Fukushima Prefecture, Japan, WAKABAYASHI GEN'ICHIRO, YAMANISHI HIROKUNI, HOHARA SHIN'YA, INAGAKI MASAYO, ITO TETSUO, HORIGUCHI TETSUO, KOJIMA KIYOSHI, SUGIURA NOBUYUKI, FURUKAWA MICHIO, 放射線, 放射線, 38(4), 155 - 158, Jul. 2013
  • Survey of Radioactive Contamination in Urban distracts of Naka-Dori Area due to Fukushima-Daiichi Nucler Plant Accident, HOHARA SHIN'YA, INAGAKI MASAYO, YAMANISHI HIROKUNI, WAKABAYASHI GEN'ICHIRO, SUGIYAMA WATARU, ITO TETSUO, 近畿大学原子力研究所年報, 近畿大学原子力研究所年報, 48, 11 - 21, Mar. 25 2012
  • 福島県川俣町における環境放射線調査, 伊藤哲夫, 古川道郎, 杉浦紳之, 山西弘城, 堀口哲男, 芳原新也, 若林源一郎, 稲垣昌代, 小島清, 村田祥之, 野間宏, KURRI KR, KURRI KR, (170), 1 - 4, Mar. 2012
  • Corrigendum: Survey of Living Environmental Land Contaminated with Radioactive Materials due to Fukushima Daiichi Nuclear Plant Accident, HOHARA Sin-ya, INAGAKI Masayo, KOJIMA Kiyoshi, YAMANISHI Hirokuni, WAKABAYASHI Genichiro, SUGIYAMA Wataru, ITOH Tetsuo, Transactions of the Atomic Energy Society of Japan, Transactions of the Atomic Energy Society of Japan, 11(4), 340 - 340, 2012
  • Environmental radiation survey in Kawamata-machi, Fukushima-ken: Measurement of radiocesium in soil and plants, H. Yamanishi, M. Inagaki, G. Wakabayashi, S. Hohara, T. Itoh, M. Furukawa, Proceedings of the International Symposium on Environmental monitoring and dose estimation of residents after accident of TEPCO’s Fukushima Daiichi Nuclear Power Station, Proceedings of the International Symposium on Environmental monitoring and dose estimation of residents after accident of TEPCO’s Fukushima Daiichi Nuclear Power Station, 49 - 52, 2012 , Refereed
  • Survey of living environmental land contaminated with radioactive materials due to Fukushima Daiichi nuclear plant accident, Sin-Ya Hohara, Masayo Inagaki, Kiyoshi Kojima, Hirokuni Yamanishi, Genichiro Wakabayashi, Wataru Sugiyama, Tetsuo Itoh, Transactions of the Atomic Energy Society of Japan, Transactions of the Atomic Energy Society of Japan, 10(3), 145 - 148, Sep. 2011
    Summary:Radioactive materials were released to the general environment due to the accident at the Fukushima Daiichi nuclear power station. The released radioactive materials fell and contaminated the land mainly in the Tohoku and Kanto areas of Japan. We surveyed the air dose rate in relation to the pave condition of the land, and investigated the contamination level in some nonpaved areas at the center of Fukushima City, Koriyama City, and Nasushiobara City. From the survey results, the dose rates of the nonpaved areas were found to be higher than those of the paved areas, and the dose rates of the paved areas depend on the paving materials of the area. The contamination level of the nonpaved area in Nasushiobara City was below the regulation level of specific activities in a radiation-controlled area in Japan. However, the contamination levels in the nonpaved areas in Fukushima City and Koriyama City were above the regulation level. © 2011 Atomic Energy Society of Japan, All Rights Reserved.
  • Development of NaI Survey Protocol for Induced Radioactive Materials on Clearance,, H. Yamanishi, A. Sabourov, M. Kerimbaev, J.C.Liu, Progress in Nuclear Science and Technology, Progress in Nuclear Science and Technology, 1, 505 - 508, 2011 , Refereed
  • Burst X-ray detection using RMSAFE, H Yamanishi, H Miyake, J Kodaira, H Obayashi, M Isobe, K Matsuoka, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 501(2-3), 589 - 593, Apr. 2003
    Summary:The function of the radiation monitoring system Radiation Monitoring System Applicable to Fusion Experiments (RMSAFE) is well verified to detect burst radiation, that is, radiation generated suddenly and explosively. When an increase in 50 ms integrated count from a radiation monitor, which is recorded and updated every 10 ms in the system CPU. is encountered to exceed a pre-set level, RMSAFE recognizes it as an outbreak of burst radiation and alters its recording mode so that the burst event data is saved in a specified file. In this study, we detected X-rays arising from Compact Helical System (CHS), a high-temperature plasma experimental device, in order to verify that RMSAFE is able to detect radiation bursts successfully and accurately. Increases in the dose of radiation due to X-rays from CHS were observed concurrently at various observation points in several plasma shots. The weekly accumulated values of radiation dose observed by RMSAFE in the CHS torus hall were consistent with the results of integrated dose measurements by thermoluminescent dosimeter (TLD) and by radiophotoluminescent dosimeter (RPLD), and furthermore, the general decreasing tendency of the observed dose with the distance from the CHS torus was clearly seen, though detailed radiation patterns might be dependent on source plasma and other conditions. These results support our conclusion that RMSAFE is able to successfully detect burst X-rays. (C) 2003 Elsevier Science B.V. All rights reserved.
  • Separation of natural background by using correlation of time-series data on radiation monitoring, H Yamanishi, H Miyake, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 40(1), 44 - 48, Jan. 2003
    Summary:Increase of dose rate due to rainfall often becomes an interfering factor for radiation monitoring outdoors. However, the nature of this interference is different at each place. We obtained a good correlation of dose rate between monitoring points by analysis of 10 minutes-series data of rainy days. The regression line formula for each point was derived from the relation of its dose rate with that of a basis point selected from among the monitoring points. Dose rate drifting due to rain at one point could be reconstructed from this formula and the measured value of the basis point. The estimated dose differed from the measured data by less than 1.2 nSv/10 min. In addition, a simulation was conducted by which virtual doses from the facility were added to actual measured values at each point. By applying the method in this study, virtual doses were calculated within 10% error when they were larger than 33 nSv. This procedure of dose evaluation can be applied to outdoor radiation monitoring if there are several radiation monitors in a site.
  • Accuracy of neutron dose evaluation in the area monitoring for LHD experiments, H Yamanishi, H Miyake, T Uda, S Tanahashi, M Saitou, H Handa, FUSION ENGINEERING AND DESIGN, FUSION ENGINEERING AND DESIGN, 51-52, 647 - 652, Nov. 2000
    Summary:The error in the evaluation of neutron dose during calculation of the neutron field around the large helical device (LHD) in D-D operation is discussed. The expected neutron dose at each monitoring point was derived from the dose conversion factor and neutron fluence data, which was calculated with the radiation transport code DOT-3.5. In contrast, the detected dose at the neutron counter was obtained from the fluence data and the detector response given by calculation with MCNP-4b. The neutron counter used in these calculations consisted of a helium-3 proportional counter with a cylindrical polyethylene moderator. According to the results of the calculations, the ratio of the detected dose to the expected dose was found to lie in the range 1.0-3.0 on the outdoor monitoring points. Since the response of a single neutron counter may lead to inconsistencies in the dose conversion factor, we attempted to minimize these inconsistencies by using a pair of counters with moderators of different thickness. The ratio of the detected dose to the expected dose ranged from 1.5 to 2.1 at the site boundary, indicating that the use of a paired counter allows a more accurate evaluation of dose than the use of a single counter. (C) 2000 Elsevier Science B.V. All rights reserved.
  • Design and development of the Flibe blanket for helical-type fusion reactor FFHR, A Sagara, H Yamanishi, S Imagawa, T Muroga, T Uda, T Noda, S Takahashi, K Fukumoto, T Yamamoto, H Matsui, A Kohyama, H Hasizume, S Toda, A Shimizu, A Suzuki, Y Hosoya, S Tanaka, T Terai, DK Sze, O Motojima, FUSION ENGINEERING AND DESIGN, FUSION ENGINEERING AND DESIGN, 49-50, 661 - 666, Nov. 2000
    Summary:Blanket design is in progress in helical-type compact reactor FFHR-2. A localized blanket concept is proposed by selecting molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with the high magnetic field design in force-free helical reactor (FFHR). Numerical results are presented on nuclear analyses using the MCNP-4B code, on thermal and stress analyses using the ABAQUS code, and heat exchange efficiency from Flibe to He. R&D programs on Flibe engineering are also in progress in material dipping-tests and in construction of molten salt loop. Preliminary results in these experiments are also presented. (C) 2000 Elsevier Science B.V. All rights reserved.
  • Three-dimensional radiation shielding analysis of the large helical device, H Handa, M Saitou, K Hayashi, H Yamanishi, K Nishimura, H Yamada, O Motojima, K Yamada, S Kamogawa, FUSION ENGINEERING AND DESIGN, FUSION ENGINEERING AND DESIGN, 43(1), 59 - 74, Oct. 1998
    Summary:Three-dimensional radiation shielding analysis around a large helical device (LHD) has been performed in order to confirm the margin of the present shielding design and to provide more detail information on a radiation environment for machine design and operation planning. Calculations were carried out using three-dimensional Sn code TORT and 25 group cross-section data based on the JENDL-3 library, and shielding characteristic were examined. Consequently, the radiation leakage effect due to the helical-shaped plasma and coils is necessary to be considered in the evaluation of the radiation flux distribution and its related evaluation: nuclear heat generation inside the cryostat. The present design method based on two-dimensional calculations was compared with three-dimensional calculations, and turned out to be an appropriate method with a suitable conservativeness with regard to the leakage source term calculation. (C) 1998 Elsevier Science S.A. All rights reserved.
  • Design studies on nuclear properties on the Flibe blanker for helical-type fusion reactor FFHR, Fusion Eng. and Design, Fusion Eng. and Design, 41, 583 - 588, 1998
  • Radiation safety considerations for LHD experiments, T Uda, H Yamanishi, H Miyake, J Kodaira, Y Sakuma, H Hirabayashi, H Obayashi, H Yamada, O Motojima, JOURNAL OF FUSION ENERGY, JOURNAL OF FUSION ENERGY, 16(1-2), 167 - 173, Jun. 1997
    Summary:For experiments with the Large Helical Device (LHD) which is now under construction at the Toki site in Japan, radiation safety issues were discussed. In the course of plasma experiments, radiations such as X-rays, induced gamma-rays, and neutrons increase. From a safety point of view, these radiation exposures to the environment should be controlled to limit the annual dose to less than 50 mu Sv at the site boundary. In order to meet this, an area monitoring system named RMSAFE (Radiation Monitoring System Applicable to Fusion Experiments) has been developed and partly installed. This can discriminate and measure radiations including burst-like emissions due to plasma shots from natural radiations. For the present period, this system is operating to monitor the natural radiation levels before the LHD operation. It was observed that the radiation levels strongly depend on rain levels and ground state. An indoor area monitoring system has already been implemented on site, to measure radiations from NBI and ECH test shots, and it shows good monitoring ability. Also, thermoluminescence dosimetry has been applied. The importance of investigating the radiological behavior under natural conditions with continuous monitoring is shown.
  • RADIATION SHIELDING ANALYSIS OF A LARGE HELICAL DEVICE, H HANDA, K HAYASHI, H YAMANISHI, Y SAKUMA, H KANEKO, H OBAYASHI, O MOTOJIMA, Y OGAWA, K YAMADA, T ABE, FUSION ENGINEERING AND DESIGN, FUSION ENGINEERING AND DESIGN, 28(1/4), 515 - 524, Mar. 1995
    Summary:Radiation shielding analysis of a large helical device (LHD) has been performed to provide information on a radiation environment needed for equipment design and operation planning. First, the applicability of the JENDL-3 library which was applied to the shielding calculations of the LHD was tested by means of a benchmark experiment on the shielding efficiency of ordinary concrete carried out at the fusion neutronics source facility at JAERI. Benchmark analysis was carried out with the MCNP continuous energy Monte Carlo code to test the JENDL-3 library itself. The same benchmark calculation was carried out with the DOT3.5 code to examine the groupwise cross-section library of FUSION-40 processed from JENDL-3. Secondly, the evaluation of the following items with the DOT3.5 code was revised, using FUSION-40 instead of the formerly used GICX-40 library: (1) dose distribution inside and outside the LHD building; (2) dose distribution inside the cellar of the LHD building resulting from steamed radiations; (3) Environmental dose distribution resulting from sky-shine effect; (4) activity and dose rate levels of vacuum vessel and superconducting magnet.
  • Separation methods of TLD dose componets for environmental radiation monitoring(共著), Yus R. AKHMAD, Yukimasa IKEBE, Michikuni SHIMO, Takao IIDA, Haruo OBAYASHI, Youichi SAKUMA, Hirokuni YAMANISHI, Jun-ichi KODAIRA, Japanise Journal of Health physics, Japanise Journal of Health physics, 29(4), 399 - 409, 1994
  • RELATIONSHIP BETWEEN RADON EXHALATION RATE FROM GROUND AND ATMOSPHERIC RADON CONCENTRATION, Y IKEBE, H YAMANISHI, K TOJO, T IIDA, JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 35(8), 735 - 738, Aug. 1993
  • OPTIMAL MONITORING NETWORK DESIGN FOR MEASURING REGIONAL DISTRIBUTION OF ATMOSPHERIC RADON CONCENTRATION, H YAMANISHI, Y IKEBE, T IIDA, JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 35(4), 329 - 337, Apr. 1993
    Summary:The optimal monitoring network design for measuring regional distribution of atmospheric Rn-222 concentration was discussed in the area around the Nohbi-Plains as an example. The representativeness and the optimal allocation of monitoring stations were analyzed under an assumption that the concentration distribution calculated by simple interpolation of measured values was true. An allocation method based on representativeness of stations using information of measured concentration distribution was analyzed first. The result showed that almost the same distribution of concentration could be obtained with the half of existing stations. The method will be best used in reconsidering a monitoring network. Secondly, an allocation method using information of Rn-222 source distribution instead of its atmospheric concentration and another one in which the total object area was equally divided were discussed with a view to applying it to the areas where the regional distribution of Rn-222 concentration had not been measured. The result showed that the allocation based on the equal division is suitable for limited small number of stations while the allocation using Rn-222 source distribution is suitable for obtaining detail concentration pattern.
  • MEASUREMENTS OF REGIONAL DISTRIBUTION OF RN-222 CONCENTRATION, H YAMANISHI, T IIDA, Y IKEBE, S ABE, T HATA, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 28(4), 331 - 338, Apr. 1991
    Summary:Outdoor Rn-222 concentrations were measured with electrostatic integrating radon monitors (EIRM) at 40 points around Nagoya, in which 15 sets of 2-month-exposure data over 2.5 yr were obtained. Seasonal variation of Rn-222 concentration showed a clear pattern which had a spring-to-summer minimum and an autumn-to-winter maximum. Annual means Rn-222 concentration ranged 3.5 approximately 11.7 Bq.m-3 depending on locations. Higher concentrations were obtained in mountainous regions while lower concentrations were obtained near the sea. The relation between atmospheric Rn-222 concentration and uranium content of granitic rocks was also discussed. High level Rn-222 concentrations were obtained over areas of granitic rocks which were comparatively uranium-rich. As an almost linear relationship was recognized between the Rn-222 concentration and exposure rate due to external natural radiation, a close correlation was anticipated between the concentration and Ra-226 content of soil. From the obtained regional distribution of Rn-222 concentration, per caput lung dose in the area was estimated to be about 0.44 +/- 0.11 mSv.yr-1.
  • 短寿命α核種等のRI利用における合理的な放射線安全管理のあり方に関する研究, 細野 眞, 織内 昇, 右近 直之, 永津 弘太郎, 伊藤 哲夫, 山西 弘城, 松田 外志朗, 山田 崇裕, 蜂須賀 暁子, 中村 吉秀, 核医学, 核医学, 55(Suppl.), S215 - S215, Nov. 2018 , Refereed
  • Time trend change of air dose rate on Paved areas in Fukushima city after the Fukushima Daiichi NPP accident, Sin-Ya Hohara, Masayo Inagaki, Hirokuni Yamanishi, Genichiro Wakabayashi, Wataru Sugiyama, Tetsuo Itoh, Radiation Monitoring and Dose Estimation of the Fukushima Nuclear Accident, Radiation Monitoring and Dose Estimation of the Fukushima Nuclear Accident, 103 - 113, Jan. 01 2014 , Refereed
    Summary:The Kinki University Atomic Energy Research Institute investigated radioactive contamination resulting from the Fukushima Daiichi Nuclear Power Plant accident in urban areas of Fukushima City, Fukushima Prefecture, Japan. Activity measurement of the surface soil and a survey of the dose rate distribution in urban areas were performed. From the results of this research, dose rate changes in paved areas became clear, and gradients of the dose rate decrease for different paving materials were measured and analyzed.
  • DEPTH PROFILE OF TRITIUM PRODUCTION IN CONCRETE AROUND A FUSION DEVICE, Hirokuni Yamanishi, FUSION SCIENCE AND TECHNOLOGY, FUSION SCIENCE AND TECHNOLOGY, 60(3), 1033 - 1036, Oct. 2011 , Refereed
    Summary:The depth profile of tritium in concrete near a fusion device has been calculated from an energy spectrum data of neutron which can be obtained by means of a radiation transport calculation code. The production of tritium increases gradually up to 8 cm depth in concrete, and the concentration at this depth is 1.5 times of that near the surface. The concentration will be 12 kBq/cm(3) at the maximum point in concrete after 30 years operation at 3 GW fusion power. These profile data of tritium in concrete are useful for decommissioning of a facility.
  • DESIGN OF AN INTEGRATING TYPE NEUTRON DOSE MONITOR, Hirokuni Yamanishi, RADIATION PROTECTION DOSIMETRY, RADIATION PROTECTION DOSIMETRY, 146(1-3), 126 - 128, Jul. 2011 , Refereed
    Summary:It is intended that deuterium-deuterium reaction experiments will be performed for the next phase of the large helical device (LHD) at National Institute for Fusion Science (NIFS), Toki, Japan. To protect workers against radiation, the characteristics of the radiation field at the LHD workplace should be evaluated. The neutron fluence at the workplace was calculated by means of the radiation transportation code. Since the neutron energy distribution at the workplace has a wide energy range, from thermal to fast neutrons, a neutron dose monitor had to be especially designed. The author designed an integrating type neutron dose monitor for this purpose. Since this monitor has good responses for dose evaluation in every energy range, it should be able to evaluate the dose at the LHD workplace accurately.
  • Study on the calibration of LHD neutron monitoring system, Naoto Nishio, Atsushi Yamazaki, Kenichi Watanabe, Akira Uritani, Mitsutaka Isobe, Hirokuni Yamanishi, Plasma and Fusion Research, Plasma and Fusion Research, 6(1), 2011 , Refereed
    Summary:Neutron monitoring is quite important because neutron yield generated by fusion reactions corresponds to the fusion output. In design of the neutron monitor, Monte Carlo simulations play an important role to make corrections on various parameters, such as neutron energy spectrum and spatial distribution when determining the calibration constant. We consider the calibration procedures using a Cf point source toroidally rotating in the vacuum vessel, and evaluate uncertainties of the calibration constant for the neutron detector placed on the center axis. © 2011 The Japan Society of Plasma Science and Nuclear Fusion Research.
  • Behavior of environmental tritium at NIFS Toki site of Japan, S. Sugihara, M. Tanaka, T. Tamari, J. Shimada, T. Takahashi, N. Momoshima, S. Fukutani, M. Atarashi-Andoh, Y. Sakuma, S. Yokoyama, K. Miyamoto, H. Amancr, H. Yamanishi, T. Uda, Fusion Science and Technology, Fusion Science and Technology, 60(4), 1300 - 1303, 2011 , Refereed
    Summary:The levels of tritium in the atmosphere are nowadays almost only of natural origin and of the same range as before the era of the nuclear tests. In order to appraise the influence of tritium released from nuclear facilities to the environment, it is necessary to confirm the effect of tritium appearing overlapped on background tritium levels. Tritium concentrations and stable isotopes of oxygen and hydrogen in rain water, stream water and groundwater at the NIFS (National Institute for Fusion Science, Gifu prefecture, Japan) site were analyzed to understand behavior of the natural tritium in coupling with rain event. Conductivity, temperature and flow rate of the stream were monitored continuously. The range of tritium concentrations in rain for three year period was 0.09-0.78 Bq/l (average 0.37+0.14 Bq/l). The tritium concentrations of stream water and groundwater were almost constant, 0.34 Bq/l and 0.25 Bq/l, respectively. The isotopic ratio of oxygen and hydrogen showed a typical seasonal pattern observed in Japan. Two component separation analysis was carried out for the stream water at the time of rain using isotopic ratio, conductivity and tritium concentration.
  • Method of H*(10) evaluation using a spherical-type energy-independent neutron dose monitor, S. H. Bhuiya, H. Yamanishi, T. Uda, RADIATION MEASUREMENTS, RADIATION MEASUREMENTS, 45(10), 1096 - 1102, Dec. 2010 , Refereed
    Summary:A spherical-type neutron dose monitor has been developed for the use of area monitoring around the neutron producing fields. Considering the practical fields that neutrons coming from multiple directions, the study has been performed using MCNP simulation, in order to estimate the resultant direction of the sources and to find a suitable method of H*(10) evaluation. This was done by irradiating the monitor using two neutron sources of different energies and intensities; placed at an angle between them. A parallel neutron beam of 50 cm radius with wide energy was used for the irradiation. The direction of the neutron sources was determined comparing the responses of 12 thermo-luminescent detectors (TLDs) of first layer between single and two directional sources. It was found that in most of the cases, the direction of the source was estimated to be the average angle or near the average angle of single sources. Using a linear combinational equation the method has been developed for evaluating the dose from the mean values of selected detectors of two consecutive depths of TLDs and the TLD of core depth. It was found that the ratio of the calculated to the expected dose was almost close to unity which indicates that the method can be used for evaluating the dose with good accuracy. (C) 2010 Elsevier Ltd. All rights reserved.
  • Fusion product diagnostics planned for Large Helical Device deuterium experiment, M. Isobe, H. Yamanishi, M. Osakabe, H. Miyake, H. Tomita, K. Watanabe, H. Iwai, Y. Nomura, N. Nishio, K. Ishii, J. H. Kaneko, J. Kawarabayashi, E. Takada, A. Uritani, M. Sasao, T. Iguchi, Y. Takeiri, H. Yamada, Review of Scientific Instruments, Review of Scientific Instruments, 81(10), Oct. 2010 , Refereed
    Summary:Deuterium experiment on the Large Helical Device (LHD) is now being planned at the National Institute for Fusion Science. The fusion product diagnostics systems currently considered for installation on LHD are described in this paper. The systems will include a time-resolved neutron yield monitor based on neutron gas counters, a time-integrated neutron yield monitor based on activation techniques, a multicollimator scintillation detector array for diagnosing spatial distribution of neutron emission rate, 2.5 MeV neutron spectrometer, 14 MeV neutron counter, and prompt γ -ray diagnostics. © 2010 American Institute of Physics.
  • A study on the neutron monitoring system of LHD based on Monte Carlo simulations, N. Nishio, S. Yamamoto, K. Watanabe, A. Uritani, M. Isobe, H. Yamanishi, Review of Scientific Instruments, Review of Scientific Instruments, 81(10), Oct. 2010 , Refereed
    Summary:Neutron monitoring is quite important because fusion neutrons are a direct evidence of fusion reactions. In calibration experiments of a neutron monitoring system, Monte Carlo calculations play an important role to correct various effects. To perform Monte Carlo calculations for a helical type fusion device, we make a program that can automatically generate an input file of a helical coil geometry for the MCNP code. The neutron spatial distributions and spectra for the helical devices are calculated in the geometries automatically generated by this program. We also discuss in calibration experiments. © 2010 American Institute of Physics.
  • Evaluation of H*(10) using the developed spherical type neutron dose monitor, S. H. Bhuiya, H. Yamanishi, T. Uda, RADIATION PROTECTION DOSIMETRY, RADIATION PROTECTION DOSIMETRY, 141(3), 217 - 221, Oct. 2010 , Refereed
    Summary:An instrument for evaluating the neutron ambient dose equivalent has been developed. It has the characteristic of uniform response to wide energy of neutrons. The monitor is four-layered spherically shaped, based on moderation and absorption of neutrons. Neutron dose can be evaluated from the linear combination of three specific responses of thermoluminescent dosemeters (TLDs), which are located at three depths in the moderator. TLDs were arranged between layers of two consecutive depths on 12 radial axes at even intervals so that the monitor is equally sensitive to all directions of neutrons. In order to verify the usefulness of dose evaluation by the monitor, irradiation experiments were conducted at the FRS, JAEA. The D(2)O-moderated (252)Cf was used for the calibration of the monitor. Experiments were also conducted by using two neutron sources of (252)Cf bare and (241)Am-Be. As a result, the evaluated dose for each irradiation was obtained close to the actual irradiated dose. It was confirmed that the method of dose evaluation by the developed monitor can be applied to practical neutron fields where the distance of neutron source is unknown.
  • Design of an energy-independent spherical-type neutron dose monitor, Sariful Haque Bhuiya, Hirokuni Yamanishi, Tatsuhiko Uda, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 607(3), 629 - 633, Aug. 2009 , Refereed
    Summary:The thickness of a spherical-type neutron dose monitor has been optimized in order to obtain improved dose response compared to that of existing instruments. The monitor structure includes four layers of the spherical shell. The outermost layer is composed of a poly-methyl methacrylate (PMMA) shell. A boron nitride shell is used as the second layer while two polyethylene shells are used as the third and the core layers. Twelve radial directional thermo-luminescent detectors (TLD) detectors are arranged between the layers at two different depths and one in the center. Considering the reaction rate of (6)Li(n,alpha) T for the TLD detectors, a series of calculations were performed using MCNP5 by varying the thickness of the layers. Neutron cross-section libraries based on JENDL-3.3 were applied for the calculations. To evaluate the dose response of the monitor, the spectrum of the D(2)O-moderated (252)Cf source was used as mentioned in ISO 8529. The monitor is sensitive to measurements of three different energy groups at three depths of the moderator. The neutron dose was calculated from the responses of a linear combination of TLD group detectors. The dose response was improved and well agree with expected dose, H*(10), compared to that of existing instruments, especially for intermediate energies of neutrons. The total ambient dose equivalent was varied only 3% for two different incident directions, hence the direction distribution was found small for dose measurement. (C) 2009 Elsevier B.V. All rights reserved.
  • Correlation between neutron component and ionizing component of cosmic ray dose in concrete buildings, H. Yamanishi, Radioisotopes, Radioisotopes, 55(7), 385 - 389, 2006
  • Design of a portable directional neutron source finder, H Yamanishi, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT, 544(3), 643 - 648, Jun. 2005
    Summary:An instrument that determines the direction of a remote existing neutron source has been designed. This instrument combines a polyethylene block and four He-3 counter tubes. The advantages of the instrument are portability and good angular resolution. The count from the detector was varied with the neutron incident angle due to the moderator. Using this characteristic, the direction of the neutron source can be measured precisely by revising the axis of the instrument so that the difference between the four detectors measurements is minimized. Consequently, the direction of the central axis of the instrument in which the response difference of the four detectors reaches a minimum indicates the direction of the neutron source. The practical use of the instrument was demonstrated by Cf-252 source irradiation experiment and MCNP simulation. (c) 2005 Elsevier B.V. All rights reserved.
  • Variation of terrestrial gamma radiation in Toki, Japan-comparison between gamma-ray spectrometry using Ge semiconductor and ICP-MS measurement, Y. Fujikawa, M. Fukui, T. Baba, T. Yoshimoto, E. Ikeda, M. Saito, H. Yamanishi, T. Uda, International Congress Series, International Congress Series, 1276, 415 - 417, Feb. 2005 , Refereed
    Summary:The cause of the spatial variation in external radiation levels in the Toki area in Japan was investigated by in-situ measurements of gamma-ray spectrum and by collections and measurements of soil samples. It was found that the radionuclide contents of topsoil largely governed the radiation level while land exploitation, gardening activities, and concrete-building constructions caused the variation in radiation there. © 2004 Elsevier B.V. All rights reserved.
  • Design of a multi-layer-type neutron monitor for measuring dose of three energy groups, J. Nuclear Science and Technology, J. Nuclear Science and Technology, Supplement 4 (March 2004), 392-394, 2004
  • Development of an environmental atmospheric tritium monitoring system at the Toki site, K. Shinotsuka, H. Yamanishi, Y. Sakuma, M. Tanaka, N. Tsuji, T. Uda, Journal of Radioanalytical and Nuclear Chemistry, Journal of Radioanalytical and Nuclear Chemistry, 258(2), 233 - 241, Nov. 2003 , Refereed
    Summary:In this study, the application for monitoring atmospheric tritium at the site of nuclear fusion facility is presented. Construction and examination of the tritium sampler and its arrangement at the site are mainly discussed. Atmospheric tritium concentrations at Toki site were determined in the sampling period from September 2000 to June 2001. Although the data for HTO were low because of their low specific activity (0.62 Bq/l), our average HT and CH 3T data were 9.1 and 3.3 mBq/m3, respectively, and systematically lower than the previously reported values at the same site, even if the considerable decay correction was carried out. Suitable monitoring points are discussed by considering the local meteorological features at the Toki site. Since the wind conditions at this site were governed by diurnal and nocturnal wind blowing to the contrary directions, it is concluded that the monitoring points should be placed at the site boundary of downwind direction of these winds. Considering that the expected levels of effluent tritium in the D-D experiment at the National Institute for Fusion Science are competitive with those in the environment, the detailed variations of the environmental tritium should be comprehended to detect minute amounts of the artificial tritium.
  • Removal of the impurities from environmental water samples for tritium measurement by liquid scintillation counting, Y Sakuma, Y Ogata, N Tsuji, H Yamanishi, T Iida, JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 255(2), 325 - 327, 2003 , Refereed
    Summary:Liquid scintillation counting is the most popular method for tritium measurement, however, it takes much time and a lot of doing to distill off the impurities before mixing the sample water and liquid scintillation cocktail. We have investigated the possibility of an alternative method to the distillation. We have found out that the filtration can be an alternative to distillation for the environmental water samples before electrolytic enrichment.
  • Proposal for a portable directional neutron source finder, Jpn. J. Health Phys., Jpn. J. Health Phys., 38(3), 267-269, 2003
  • Uranium and plutonium isotope ratio measurement as a tool for environmental monitoring - experiences in Osaka, Gifu and Hiroshima, Japan, Yoko Fujikawa, Kiyoshi Shizuma, Emi Ikeda, Takahiro Baba, Takaaki Yoshimoto, Masami Fukui, Masahiro Saito, Hirokuni Yamanishi, Tatsuhiko Uda, Journal of Nuclear Science and Technology, Journal of Nuclear Science and Technology, 39, 564 - 567, 2002 , Refereed
    Summary:We measured U-234/U-238, U-235/U-238 and Pu-239/240 isotope ratios in soil samples from Osaka, Gifu, and Hiroshima, Japan by inductively coupled plasma - quadrupole mass spectrometry. Deviation in U-235/U-238 isotope ratio from natural ratio was not found in soil collected three days after A-bomb detonation in Hiroshima, where approximately 50 kg of U-235 should have been discharged. U-234/U-238 ratio variation in soil that was dependent on the soil particle size and soil digestion procedure was found. Variation in Pu-240/Pu-239 ratio due to incomplete dissolution of soil samples was found in soil from Osaka. The results indicated the necessity of further investigation on natural variation of U isotope ratios in Japanese environment, and selection of sample processing technique depending on sample characteristics in order to obtain accurate isotope ratio. © 2002 Atomic Energy Society of Japan.
  • Dependence on Incident Angle of Solid State Detector Response to Gamma-Rays, Hirokuni Yamanishi, Satarou Yamaguchi, Takayuki Yamaguchi, Kohtaro Ueki, Transactions of the Atomic Energy Society of Japan, Transactions of the Atomic Energy Society of Japan, 1(1), 15 - 19, 2002
    Summary:The shape and size of a NaI(T1) scintillator that should maximize response variation with γ-ray incident angle was estimated by analytical model calculation. It proved that, even for gamma rays of energy exceeding 1 MeV, a slab detector measuring 50 cm x 50 cm x 5 cm thick should present a ratio of at least 4 between maximum and minimum responses against incidence at different angles. For a sample case of 60 keV gamma rays, estimation of the incident angle dependence by means of Monte Carlo simulation agreed well with experiment using a CZT detector. The counts from photoelectric peak varied with incident angle roughly along a sine curve. The foregoing finding served as basis for proposing a practical direction finder for γ-ray source operating on the principle of determining the source direction from variations in count with incident angle. © 2002, Atomic Energy Society of Japan. All rights reserved.
  • Studies on Flibe blanket designs in Helical Reactor FFHR, A Sagara, H Yamanishi, T Uda, M Osamu, T Kunugi, Y Matsumoto, Y Wu, H Matsui, S Takahasi, T Yamamoto, S Toda, O Mitarai, S Satake, T Terai, S Fukada, FUSION TECHNOLOGY, FUSION TECHNOLOGY, 39(2), 753 - 757, Mar. 2001
    Summary:The self-cooling molten-salt Flibe blanket of FFHR is numerically analyzed, resulting the optimum first wall to be as thin as 5mm and the heat flux up to 0.25MW/m(2) to be feasible with adopting V-4Cr-4Ti as the structural material. An alternative concept of free surface using a capillary force is shown to be feasible even in helical systems, where a spiral flow is formed and drastically enhances the heat transfer efficiency. The nuclear property of Flibe blanket is modified with increasing Be amount and adopting carbon reflector, resulting the local TBR of 1.3. As an optional technique, 50% enrichment of Li-6 gives the maximum TBR of 1.4.
  • Optimization of neutron monitoring detector for LHD experiments, Proceeding 10th International Congress of the International Radiation Protection Association., Proceeding 10th International Congress of the International Radiation Protection Association., P-3b, 159, 2000
  • Design studies of helical-type fusion reactor FFHR, A. Sagara, O. Motojima, S. Imagawa, O. Mitarai, T. Noda, T. Uda, K. Watanabe, H. Yamanishi, H. Chikaraishi, A. Kohyama, H. Matsui, T. Muroga, N. Noda, N. Ohyabu, T. Satow, A. A. Shishkin, Dai-Kai Sze, A. Suzuki, S. Tanaka, T. Terai, K. Yamazaki, J. Yamamoto, Fusion Engineering and Design, Fusion Engineering and Design, 41(1-4), 349 - 355, Sep. 01 1998 , Refereed
    Summary:The main feature of FFHR is force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt Flibe as a self-cooling tritium breeder from the main reason of safety. Collaboration works based on the LHD project have made great progress in the reactor studies by focusing on engineering aspects of the high magnetic field and Flibe system design. Encouraging positive results are shown on ignition access, mechanical stress in coils supporting structures, improvement in the blanket system including materials selection and tritium recovery. Critical issues on fundamental safety analysis and maintainability of reactor components are also discussed, and many subjects are pointed out as future works. © 1998 Elsevier Science S.A. All rights reserved.
  • Blanket design using FLiBe in helical-type fusion reactor FFHR, A Sagara, O Motojima, O Mitarai, S Imagawa, K Watanabe, H Yamanishi, H Chikaraishi, A Kohyama, H Matsui, T Muroga, N Noda, T Noda, N Ohyabu, T Satow, AA Shishkin, S Tanaka, T Terai, K Yamazaki, J Yamamoto, JOURNAL OF NUCLEAR MATERIALS, JOURNAL OF NUCLEAR MATERIALS, 248, 147 - 152, Sep. 1997 , Refereed
    Summary:The blanket design for a force-free helical reactor (FFHR) is presented, which is a demo-relevant heliotron-type D-T fusion reactor based on the first all-superconducting-coils device, LHD (large helical device) under construction in NIFS at present. For the goal of a self-ignited reactor of 3 GW thermal output, the design parameters at the first stage for concept definition of FFHR have been investigated. The main feature of FFHR is a force-free-like configuration of helical coils, which makes it possible to simplify the coil supporting structure and to use a high magnetic field instead of high plasma beta. The other feature is the selection of molten-salt FLiBe as a self-cooling tritium breeder for mainly safety reasons owing to the low tritium inventory, low reactivity with air and water, low pressure operation, and low MHD resistance compatible with a high magnetic field. In particular, as common issues in fusion reactors, the FLiBe blanket system in FFHR is expressed in detail by showing engineering possibilities to overcome key issues on tritium permeation, material corrosion, heat transfer, operation pressure, etc. The basic design for maintenance and repair of the blanket is also discussed. (C) 1997 Elsevier Science B.V.
  • Development of neutron monitoring system in n-gamma mixed field with a twin-type (10)BF3-(11)BF3 ionization chamber, T Yamamoto, H Yamanishi, Y Sakuma, T Uda, H Miyake, T Yoshimoto, T Tsujimoto, IRPA9 - 1996 INTERNATIONAL CONGRESS ON RADIATION PROTECTION / NINTH INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION, PROCEEDINGS, VOL 4, IRPA9 - 1996 INTERNATIONAL CONGRESS ON RADIATION PROTECTION / NINTH INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION, PROCEEDINGS, VOL 4, D362 - D364, 1996 , Refereed
  • Blanket and divertor design for force free helical reactor (FFHR), A. Sagara, O. Motojima, K. Watanabe, S. Imagawa, H. Yamanishi, O. Mitarai, T. Satow, H. Tikaraishi, Fusion Engineering and Design, Fusion Engineering and Design, 29(C), 51 - 56, Mar. 03 1995 , Refereed
    Summary:Conceptual design of blanket and divertor for a force free helical reactor (FFHR) is presented. The demonstration-relevant FFHR is a heliotron-type helical reactor having superconducting helical and poloidal coils based on the large helical device (LHD) which is now under construction in the National Institute for Fusion Science. The main feature of FFHR is force free configuration of helical coils, which allows us to simplify the coil supporting structure and to use high magnetic field instead of high plasma β. For the goal of a self-ignited D-T reactor of 3 GW thermal output, the design parameters for FFHR are investigated under the LHD scaling for energy confinement and density limit. In particular, to satisfy the reactor lifetime of 30 years, the engineering issues in FFHR are discussed by focusing on selection of structrual materials for 500 dpa, optimization of tritium breeding system with neutron multiplier, cooling with molten-salt Flibe and operation temperature in the blanket, radiation shielding to achieve a reduction of more than 5 orders of magnitude at superconducting coils, and steady state helium ash removal with an efficiency of around 30%. © 1995.
  • Radiation monitoring system developed for fusion site in Toki(共著), Fusion Technology 1994, Fusion Technology 1994, 1421 - 1424, 1995
  • MEASUREMENTS OF REGIONAL DISTRIBUTION OF 222RN CONCENTRATION AND ANALYSIS ON OPTIMAL ALLOCATION OF MONITORING STATIONS, H YAMANISHI, Y IKEBE, T IIDA, IRPA8 - EIGHTH INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION - WORLDWIDE ACHIEVEMENT IN PUBLIC AND OCCUPATIONAL HEALTH PROTECTION AGAINST RADIATION, VOL II, IRPA8 - EIGHTH INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION - WORLDWIDE ACHIEVEMENT IN PUBLIC AND OCCUPATIONAL HEALTH PROTECTION AGAINST RADIATION, VOL II, 1387 - 1390, 1992 , Refereed

Conference Activities & Talks

  • Migration of radioactive cesium to water from grass and fallen leaves, H.Yamanishi, M.Inagaki, G.Wakabayashi, S.Hohara, T.Itoh, M.Furukawa, International Symposium on Radiological Issues for Fukushima’s Revitalized Future,   2015 05
  • Survey of Environmental Radiation in Kawamata-machi, Fukushima-ken ~Measurement of radioactive cesium in soil and plant~, H.Yamanishi, M.Inagaki, G.Wakabayashi, S.Hohara, T.Itoh, M.Furukawa, International Symposium on Environmental monitoring and dose estimation of residents after accident of TEPCO's Fukushima Daiichi Nuclear Power Stations,   2014 12
  • Migration of radioactive cesium containing in grass or fallen leaves to water, H.Yamanishi, M.Inagaki, G.Wakabayashi, S.Hohara, T.Itoh, M.Furukawa, The 9th International Symposium on the Natural Radiation Environment (NRE-IX),   2014 09
  • Mat-forming cyanobacteria effectively decontaminate radioactive cesium.,   2013 05
  • Development and utilization of gamma-ray shielding suit excellent easy-to-wear, T. Itoh, H. Yamanishi, T. Yamamoto, T. Yamamoto, K. Yamamoto, 13th Intern. Congress of the International Radiation Protection Association,   2012 05

Works

  • Sensitivity of radiation detector for cosmic ray
  • Variation of radon and its progeny concentration in a room.

Misc

  • 放射性セシウム吸着ブロックの開発とその適用に関する検討, 山西弘城, 荒川剛, 奥村博司, 緒方文彦, 稲垣昌代, 伊藤哲夫, 日本保健物理学会研究発表会講演要旨集, 50th, 201,   2017 , http://jglobal.jst.go.jp/public/201702280857284639
  • 環境負荷の小さな化学物質を用いた土壌中放射性セシウムの溶出の検討, 石渡 俊二, 多賀 淳, 緒方 文彦, 北小路 学, 山西 弘城, 稲垣 昌代, 伊藤 哲夫, 古川 道郎, 日本保健物理学会研究発表会講演要旨集, 48回, 114, 114,   2015 07
  • Survey of radioactive contamination in Fukushima Naka-dori region, Fukushima, Japan (The 12th International Conference on Radiation Shielding (ICRS-12) and the 17th Topical Meeting of the Radiation Protection and Shielding Division of ANS (RPSD-2012)) --, Hohara Sin-ya, Inagaki Masayo, Yamanishi Hirokuni, Progress in nuclear science and technology, 4, 39, 42,   2014 04 , 10.15669/pnst.4.39, http://ci.nii.ac.jp/naid/40020091859
  • 福島第1原子力発電所事故に起因する土壌中放射性セシウムの分布,溶出,吸着に関する研究, YAMANISHI HIROKUNI, INAGAKI MASAYO, WAKABAYASHI GEN'ICHIRO, HOHARA SHIN'YA, ITO TETSUO, ISHIWATA SHUNJI, TAGA ATSUSHI, OGATA FUMIHIKO, FURUKAWA MICHIO, 日本保健物理学会研究発表会講演要旨集, 46th, 136,   2013 06 24 , http://jglobal.jst.go.jp/detail.php?from=API&JGLOBAL_ID=201302290314729695
  • Time Trend Change of Dose Rate on paved area in Fukushima City, Hohara Sin-ya, Inagaki Masayo, Yamanishi Hirokuni, Wakabayashi Genichiro, Sugiyama Wataru, Itoh Tetsuo, Proceedings of AESJ, 2013, 0,   2013 , 10.11561/aesj.2013s.0.663.0, http://ci.nii.ac.jp/naid/130004568671
    Summary:2011年3月の福島第一原子力発電所事故により放射性物質が一般環境中に放出され、東北・関東地方の空間線量率が上昇した。近畿大学原子力研究所は2011年4月より、福島中通地区における一般環境中の放射性汚染調査を行っている。調査の結果、舗装地においては舗装素材により空間線量率の減衰傾向が異なる事が確認されたので報告をする。
  • Cesium Removal from the Radioactive Cesium Contaminated Soil by an Electrophoresis, Ihara Tatsuhiko, Itoh Tetsuo, Yamanishi Hirokuni, Wakabayashi Genichiro, Hohara Shin-ya, Inagaki Masayo, Proceedings of AESJ, 2013, 0,   2013 , 10.11561/aesj.2013s.0.667.0, http://ci.nii.ac.jp/naid/130004568866
    Summary:放射性セシウム汚染土壌を対象に,化学物質を添加することなく電場の作用で効率よくセシウム除去できる電気泳動的手法を開発した.具体的には負電極板表面にイオン透過膜(セパレーター)を貼り付け,水を加えてスラリー状にした汚染土壌をセパレーターを介して接触させ,負電極の電場によってセパレーターと負電極間界面に引きこみ,除去する方法である.土壌としては学校校庭の表層を集めた土壌を分級し,粒子径0.125 mm以下の区分の土壌を用いた.<br> ラボスケールでの実験として,セパレーターと電極の間にイオン液体とプルシアンブルーの混合物を閉じ込めた系で10 gの土壌用いて泳動電圧100V,30分間電気泳動を行ったところ,30.5&plusmn;0.3 Bq/gを8.3&plusmn;0.2 Bq/gのレベルまで低下できることが分かった.
  • Environmental radiation research in Kawamata-cho, Fukushima -ken, Ito Tetsuo, Murata Yoshiyuki, Furukawa Michiro, Sugiura Nobuyuki, Yamanishi Hirokuni, Horiguchi Tetsuo, Hohara Shinya, Wakabayashi Genichiro, Inagaki Masayo, Kojima Kiyoshi, Proceedings of AESJ, 2011, 0, 831, 831,   2011 , http://ci.nii.ac.jp/naid/130007036161
    Summary:福島県川俣町で環境放射線調査を行なった。NaI(Tl)シンチレーションサーベイメータを用いて空間線量率の状況を把握するとともに、空間線量率の成因を分析するために、土壌を深さ毎に採取した。土壌試料について、ガンマスペクトロメトリで放射性物質濃度を定量した。その主な成分はCs-134とCs-137で、ほぼ同濃度であり、全量の90%以上が、地表面から1cmまで深さにあった。表土除去による空間線量率の低減効果についても確認した。
  • Survey of Radioactive Contaminations in cities at Fukushima-Nakadori area due to Fukushima Daiichi Nuclear Plant Accident, HOHARA SIN-YA, Inagaki Masayo, Kojima Kiyoshi, Yamanishi Hirokuni, Wakabayashi Genichiro, Itoh Tetsuo, Proceedings of AESJ, 2011, 0, 830, 830,   2011 , 10.11561/aesj.2011f.0.830.0, http://ci.nii.ac.jp/naid/130007036162
    Summary:GPS連動型の可搬型放射線位置測定装置を用いて、福島県福島市、福島県郡山市および栃木県那須塩原市の市街地における空間線量率分布の移動測定を行なった。その結果、測定を行なった市街地では、舗装地に比べて非舗装地の空間線量率が高くなる現象が観測された。また、各市街地の非舗装地における表層から0-1cmの土壌の比放射能を測定した結果、福島市内および郡山市内の公園では福島第一原発事故後1ヶ月経過した時点において数量告示に定める放射性同位元素の濃度を超えていた事がわかった。
  • Environmental radiation research in Kawamata-machi, Fukushima Pref.:(2)Reduction of air dose rate by removing suface soil, Wakabayashi Genichiro, Furukawa Michiro, Yamanishi Hirokuni, Sugiura Nobuyuki, Ito Tetsuo, Horiguchi Tetsuo, Hohara Sin-ya, Inagaki Masayo, Kojima Kiyoshi, Murata Yoshiyuki, Proceedings of AESJ, 2011, 0, 832, 832,   2011 , http://ci.nii.ac.jp/naid/130007036168
    Summary:福島県川俣町で環境放射線調査を行なった。学校の校庭や広場においてNaI(Tl)シンチレーションサーベイメータを用いた空間線量率の測定を行って線量の分布を把握した後、地表から約5 mmの表土を除去することにより、空間線量率の低減効果を調べた。学校校庭では半径2 m及び5 m、広場では半径2.4 mの表土を除去した結果、表土を除去した領域の中心で線量率は70~80%に減少した。
  • CdZnTe検出器のγ線スペクトルの入射角度依存性, 山口貴行, 山口作太郎, 山西弘城, 大林治夫, 佐久間洋一, 磯部光孝, 野村和泉, 植木紘太郎, 寺町康昌, 神野郁夫, 佐藤利和, 尾鍋秀明, 応用物理学関係連合講演会講演予稿集, 48th, 1, 130,   2001 03 28 , http://jglobal.jst.go.jp/public/201202154643522629
  • 検出部の形状効果を利用したガンマ線画像装置の開発 (II), 山西弘城, 山口作太郎, 大林治夫, 野村和泉, 植木紘太郎, 寺町康昌, 神野郁夫, 佐藤利和, 尾鍋秀明, 日本原子力学会秋の大会予稿集, 1999, 47,   1999 08 10 , http://jglobal.jst.go.jp/public/200902176287094925
  • 計測素子の形状効果を利用したガンマ線画像装置, 山口作太郎, 山西弘城, 植木紘太郎, 寺町康昌, 日本物理学会講演概要集, 53, 2, 865,   1998 09 05 , http://jglobal.jst.go.jp/public/200902160640720467
  • The proposal for gamma ray imaging device using shape efficiency of sensor., 山西弘城, 山口作太郎, 大林治夫, 佐久間洋一, 植木紘太郎, 寺町康昌, 森千鶴夫, 佐藤利和, 尾鍋秀明, 日本原子力学会秋の大会予稿集, 1998, 117,   1998 09 , http://jglobal.jst.go.jp/public/200902123368034831
  • Development of a Gamma Ray Imaging Device by means of Shape Efficiency of Sensor., 佐久間洋一, 山口作太郎, 大林治夫, 山西弘城, 磯部光孝, 植木紘太郎, 寺町康昌, 森千鶴夫, 尾鍋秀明, 応用物理学会学術講演会講演予稿集, 59th, 1, 73,   1998 09 , http://jglobal.jst.go.jp/public/200902186694781010
  • The Third Proposal for .GAMMA.-ray CCD Camera., 山西弘城, 山口作太郎, 三宅均, 植木紘太郎, 寺町康昌, 森千鶴夫, 佐藤利和, 増藤信明, 牧野俊一郎, 日本原子力学会秋の大会予稿集, 1997, 180,   1997 09 , http://jglobal.jst.go.jp/public/200902109804218070
  • A Proposal for .GAMMA.-ray CCD Camera., 山口作太郎, 牧野俊一郎, 大林治夫, 山西弘城, 植木紘太郎, 寺町康昌, 森千鶴夫, 佐藤利和, 増藤信明, 日本原子力学会秋の大会予稿集, 1996, Pt 1, 86,   1996 09 , http://jglobal.jst.go.jp/public/200902187546410735
  • Survey and decontamination of radium-223 dichloride for alpha-particle radionuclide therapy in clinical facilities, M. Hosono, S. Hohara, M. Inagaki, H. Yamanishi, G. Wakabayashi, T. Matsuda, K. Sakaguchi, K. Hanaoka, T. Ito, EUROPEAN JOURNAL OF NUCLEAR MEDICINE AND MOLECULAR IMAGING, 43, S417, S417,   2016 10
  • Measurement and parameters of alpha-emitting radium-223 for radionuclide therapy in accordance with radiation protection standards, M. Hosono, S. Hohara, H. Yamanishi, M. Inagaki, G. Wakabayashi, T. Matsuda, K. Sakaguchi, K. Hanaoka, T. Itoh, EUROPEAN JOURNAL OF NUCLEAR MEDICINE AND MOLECULAR IMAGING, 41, S329, S329,   2014 10
  • Measurement and radiation control of alpha-emitting radium-223 in radionuclide therapy for prostate cancer with bone metastases, Makoto Hosono, Sin-ya Hohara, Hirokuni Yamanishi, Masayo Inagaki, Genichiro Wakabayashi, Kenta Sakaguchi, Kohei Hanaoka, Tetsuo Itoh, JOURNAL OF NUCLEAR MEDICINE, 55,   2014 05
  • Study of safety concept for a helical-type fusion reactor, FFHR, T Uda, A Sagara, O Motojima, H Yamanishi, S Tanaka, T Terai, T Noda, FUSION ENGINEERING AND DESIGN, 42, 115, 125,   1998 09 , 10.1016/S0920-3796(97)00174-9
    Summary:Safety concepts for a force free helical reactor (FFHR), of which conceptual designs have been studied in parallel with the construction of the large helical device (LHD), are presented. The main safety features expected for the FFHR are, steady-state plasma operation, no dangerous current disruptions, and the selection of a molten-salt Flibe blanket for a tritium breeder which has low tritium inventory, self cooling effect and low chemical activity. The blanket reaches such high temperatures that the tritium permeation rate increases and this tritium must be continuously recovered. Then the first wall is expected to have a low tritium inventory. Based on the classification of the plant systems and components, it is shown that the high mobility and large radioactivity release accident accompanied with the energy release is avoidable. Fundamental safety would be secured by multiple protection systems. To prevent escalation to a severe accident caused by the fracture of any of the large radioactivity confinement components, passive and reliable active protection systems are proposed. Thus, FFHR will be designed to be as safe as possible. (C) 1998 Elsevier Science S.A. All rights reserved.
  • Effect of humidity on radon exhalation rate from concrete, H Yamanishi, H Obayashi, N Tsuji, H Nakayoshi, RADON AND THORON IN THE HUMAN ENVIRONMENT, 429, 434,   1998
    Summary:The objective of the present study is evaluation of seasonal humidity effect on radon exhalation rate from concrete. Three concrete pieces have been placed in three different fixed humidity circumstances for about a year. The three fixed humidities are selected 3,10, 25 g m(-3) in absolute humidity, those correspond to dry condition as control, winter and summer, respectively. Radon exhalation rate from each concrete piece is measured every one month during humidity exposure. Under the lower humidity, radon exhalation rate from concrete is small. On the contrary, radon exhalation rate is large in the higher humidity circumstance. This trend is consistent with the seasonal variation of indoor air radon concentration in low air-exchange-rate room.
  • Development of a dual type ionization chamber system for burst n-X mixed fields, H Yamanishi, H Hirabayashi, J Kodaira, H Miyake, H Obayashi, Y Sakuma, T Uda, T Yamamoto, IRPA9 - 1996 INTERNATIONAL CONGRESS ON RADIATION PROTECTION / NINTH INTERNATIONAL CONGRESS OF THE INTERNATIONAL RADIATION PROTECTION ASSOCIATION, PROCEEDINGS, VOL 4, 4, D359, D361,   1996
  • Measurement of air exchange rate and radon exhalation rate from building wall(共著), Proc. 7th intern. Congress, Indoor Air '96, 1, 135, 140,   1996
  • Variation of radon and radon progeny in a room with low ventilation rate, Proc. 6th intern. Congress, Indoor Air '93, 4, 549, 554,   1993

Research Grants & Projects

  • Radiation Safety for Fusion Experiment
  • Variation of radon in a room with low ventilation rates