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YAMANISHI Hirokuni

    Atomic Energy Research Institute　Professor/Director
Last Updated :2024/04/27

Researcher Information

Degree

  • Master of engineering（1988/03 Nagoya University）
  • Doctor of Engineering（1994/03 Nagoya University）

URL

J-Global ID

Research Interests

  • 環境放射線   原子炉実習   Education for radiation use   Radiation monitoring   保健物理   Natural radiation   Health Physics   

Research Areas

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

Academic & Professional Experience

  • 2019/04 - Today  Kindai universityAtomic Energy Research InstituteDirector
  • 2013/04 - Today  Kindai universityAtomic Energy Research InstituteProfessor
  • 2011/04 - 2013/03  Kindai universityAtomic Energy Research InstituteAssociate professor
  • 2006/01 - 2011/03  National Institute for Fusion ScienceSafety and Environmental Research Center助教授、准教授
  • 1991/04 - 2005/12  National Institute for Fusion ScienceSafety and Environmental Research Center助手

Education

  • 1886/04 - 1991/03  Nagoya University  Graduate School of Engineering  Nuclear Engineering
  • 1982/04 - 1986/03  Nagoya University  School of Engineering  Nuclear Engineering

Association Memberships

  • 日本保健物理学会   日本原子力学会   JAPANESE SOCIETY OF RADIATION SAFETY MANAGEMENT   

Published Papers

  • Masashi Takada; Satoru Endo; Tsuyoshi Kajimoto; Tetsuo Horiguchi; Hirokuni Yamanishi; Natsumi Yagi; Akihiko Masuda; Tetsuro Matsumoto; Hiroki Tanaka; Tomoya Nunomiya; Kei Aoyama; Masataka Narita; Takashi Nakamura
    Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment Elsevier BV 1064 169352 - 169352 0168-9002 2024/07 [Refereed]
  • Siriyaporn Sangaroon; Kunihiro Ogawa; Mitsutaka Isobe; Longyong Liao; Makoto Inami Kobayashi; Sho Toyama; Misako Miwa; Shigeo Matsuyama; Hirokuni Yamanishi; Shingo Tamaki; Isao Murata; Eiji Takada; Guoqiang Zhong; Apiwat Wisitsorasak; Nopporn Poolyarat
    IEEE Transactions on Instrumentation and Measurement Institute of Electrical and Electronics Engineers (IEEE) 72 1 - 12 0018-9456 2023/11 [Refereed]
  • Masahiro Kato; Akira Yoshida; Hirokuni Yamanishi
    Japanese Journal of Health Physics 58 (2) 69 - 72 0367-6110 2023 
    The Japanese Journal of Health Physics has shown many articles related to the accident at the TEPCO’s Fukushima Daiichi NPP in March 2011. In these, 23 articles on dosimetry and dose assessment have been published up to March 2022. The dosimetry data and dose assessment methods reported in these articles are valuable knowledge in considering future radiation monitoring methods at accidents.
  • M. Koizumi; T. Mochimaru; K. Hironaka; T. Takahashi; H. Yamanishi; G. Wakabayashi
    Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment Elsevier BV 1042 167424 - 167424 0168-9002 2022/11 [Refereed]
  • Makoto Kobayashi; Sachiko Yoshihashi; Hirokuni Yamanishi; Siriyaporn Sangaroon; Kunihiro Ogawa; Mitsutaka Isobe; Akira Uritani; Masaki Osakabe
    PLASMA AND FUSION RESEARCH JAPAN SOC PLASMA SCIENCE & NUCLEAR FUSION RESEARCH 17 1880-6821 2022/06 [Refereed]
     
    Thermal neutron flux evaluation using a single crystal diamond detector (SDD) was carried out in the core region of the UTR-KINKI reactor where a mixed radiation field by thermal and fast neutrons and gamma-ray exists. The pulse shape discrimination method to extract pulses with a rectangular shape as well as a wide pulse-width was established to exclude pulses induced by gamma-rays. The SDD, using a (LiF)-Li-6 thermal neutron converter, is able to detect pulse events caused not only by fast neutrons but also by thermal neutrons through energy depositions into the diamond by energetic alpha and triton particles induced by thermal neutrons. Additionally, the SDD without the thermal neutron converter was used for the measurement of the energy deposition events only by fast neutrons. A comparison of the pulse counts of the SDD with or without the thermal neutron convertor deduced the energy deposition spectra by thermal neutrons. The thermal neutron flux in the core region of the UTR-KINKI reactor was evaluated to be 7.6 x 10(6) n cm(-2) s(-1) W-1 up to a reactor power of 1 W. (C) 2022 The Japan Society of Plasma Science and Nuclear Fusion Research
  • Hirokuni Yamanishi; Tetsuo Ito; Makoto Hosono
    Annals of the ICRP SAGE Publications 014664532110109 - 014664532110109 0146-6453 2021/07 [Invited]
     
    This paper does not necessarily reflect the views of the International Commission on Radiological Protection. Kawamata Town in Date District, Fukushima Prefecture is located more than 30 km north-west of Fukushima Daiichi nuclear power plant, but on 22 April 2011, part of the Yamakiya District of Kawamata Town was designated as a planned evacuation area. The exposure of children was a concern in Kawamata Town. Based on the proposal of Kindai University, Kawamata Town Board of Education took the initiative to measure individual radiation doses with an integrated dosimeter (glass badge) for all kindergarten children, nursery school children, elementary school students, and junior high school students in the town. These measurements were continued for nearly 3 years from June 2011 until the end of March 2014. The total number of measurements was approximately 16,800 across 11-cycle measurement, with 3 months’ accumulation taken as one-cycle measurement. Kindai University provided financial support for the glass badge measurement service, and cooperated in the analysis of measured values and the development of advice based on the results. The main body implementing the measurements was Kawamata Town Board of Education, and the data obtained belong to Kawamata Town. When measurements were starting to be taken, schools got involved in the collection and distribution of dosimeters after explanations were provided to principals and school nurses who were in charge of risk communication. Thanks to the efforts of the schools, the recovery rate exceeded 90%, increasing the reliability of the measurements. It was clear who needed the information – the children and their parents. Kawamata Town Board of Education summarised the cumulative dose results for each measurement and notified parents via personal reports. These were sent to parents with advice on measurement results prepared by Kindai University, and care was taken to ensure that people could understand the measured results. Further briefing sessions were held as appropriate. At the briefing sessions, at the request of Kawamata Town Board of Education, the faculty members of Kindai University explained the measurement results from a professional point of view, and a professor from the Faculty of Medicine provided individual health consultations. Kawamata Town took the lead in using specialists to gain peace of mind, and this was key to the project’s success. The situation was managed by taking measurements by dosimetry, and asking experts to interpret the data and provide advice to help reassure the residents.
  • Kanoko Nishiono; Hirokuni Yamanishi
    Journal of Radiation Protection and Research Korean Association for Radiation Protection 45 (4) 154 - 162 2508-1888 2020/12 [Refereed]
  • K. Yasuda; M. Takahashi; T. Iimoto; K. Kimura; M. Inagaki; H. Yamanishi
    RADIOISOTOPES (Web) 69 (2) 1884-4111 2020 [Refereed]
  • Satoshi Iwai; Michiya Sasaki; Shogo Higaki; Hirokuni Yamanishi; Michiaki Kai; JHPS Working; Group for; Plutonium Accident in JAEA-Oarai
    JOURNAL OF RADIOLOGICAL PROTECTION IOP PUBLISHING LTD 39 (4) 1092 - 1104 0952-4746 2019/12 
    This paper describes an overview of the radiation protection response to the Plutonium intake accident that occurred at the Plutonium Fuel Facility of the Oarai Research and Development Center of the Japan Atomic Energy Agency on 6 June 2017. In the hood of the analyzing room at the Plutonium Fuel Facility five workers were checking a storage container of fast reactor nuclear fuel material. Around 11:15 a.m., vinyl bags inside the fuel material container containing Plutonium and enriched uranium burst during the inspection work. All the workers heard the bang, which caused misty dust leakage from the container. This event caused significant both skin and nasal ?-contamination for three workers and just skin ?-contamination for one worker. Decontamination was conducted in the shower room. Then the five workers were transferred to the Nuclear Fuel Cycle Engineering Laboratory to evaluate inhalation intake of Plutonium etc in the lungs. The maximum values of 2.2 & xfffd;& x5e0;10(4) Bq for Pu-239 and 2.2 & xfffd;& x5e0;10(2) Bq for Am-241 were estimated by the lung monitor. Based on these results, injection of a chelate agent was conducted for prompt excretion of Plutonium etc. The next morning, the five workers were transferred to the National Institute of Radiological Sciences for treatment including decontamination of their skin and measurement by a lung monitor. At that time no obvious energy peak was confirmed for Plutonium. The Japan Health Physics Society launched an ad-hoc working group for Plutonium intake accident around the middle of June to survey issues and to extract lessons for radiological protection. The authors, who are the members of the ad-hoc working group, here report the activity of the working group.
  • 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(Web) 55 (Supplement) 2189-9932 2018 [Refereed]
  • S.Iwai; M.Sasaki; S.Higaki; H.Yamanishi; M.Kai
    保健物理(Web) 53 (4) 1884-7560 2018 [Refereed]
  • K. Ohashi; K. Sasauchi; S. Mizuno; T. Ida; H. Yamanishi
    Journal of smart processing 高温学会 5 (3) 185 - 190 2186-702X 2016/05 [Refereed]
  • Naofumi Akata; Masahiro Tanaka; Hiromi Kato; Hirokuni Yamanishi; Hideki Kakiuchi; Hiroshi Hayashi; Hitoshi Miyake; Kiyohiko Nishimura
    PLASMA AND FUSION RESEARCH JAPAN SOC PLASMA SCIENCE & NUCLEAR FUSION RESEARCH 11 1880-6821 2016/03 [Refereed]
     
    A deuterium plasma experiment is being planned at the Large Helical Device (LHD) at the National Institute for Fusion Sciences (NIFS). To delineate the regional background tritium concentration level before initiation of the experiment, we evaluated tritium concentrations in environmental water samples (river water, pond water, well water, tap water, and rainwater) collected at Tono area, Japan since 1982. Tritium concentrations in environmental water samples ranged widely from N.D. (below the instrumental detection limit of 0.27 Bq L-1) to a maximum of 4.39 Bq L-1. Tritium concentrations at 9 continuous monitoring locations over the 15 years ranged from N.D. to 1.36 Bq L-1. This regional background concentration range will be used to evaluate environmental assessments after the initiation of the deuterium plasma experiment in LHD. (C) 2016 The Japan Society of Plasma Science and Nuclear Fusion Research
  • T. Ihara; N. Tanaka; H. Yamanishi
    スマートプロセス学会誌 = Journal of smart processing 高温学会 4 (6) 298 - 302 2186-702X 2015/11 [Refereed]
  • 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 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) 47 - 55 2015 [Refereed]
  • OHASHI Ken; SASAUCHI Ken'ichi; MIZUNO Satoru; IDA Tamio; YAMANISHI Hirokuni
    Journal of Smart Processing Smart Processing Society for Materials, Environment & Energy (High Temperature Society of Japan) 4 (6) 307 - 311 2186-702X 2015 [Refereed]
     
      In Fukushima prefecture, the full of temporal space for scrap wood, gathered deciduous leaf and wood contaminated with radioactive materials makes debris disposal not proceed now. It is considered that debris should be downsized and be stored safety until carrying to ISF (Interim Storage Facility). It is known that Biocoke has high density and poor reactivity, so we are confident that Biocoke technology is suitable to store the debris stably. In this study, leach of heavy metal and radioactive cesium from Biocoke into water was investigated in order to apply the Biocoke technology for storing debris for long time. An elution impact into landfill by combustion ash of Biocoke has been shown allowable value or less. In Elution testing of radioactive cesium from Biocoke to water, it could be demonstrated to suppress to 1/4 by Biocoke technology.
  • ARAKAWA Tsuyoshi; YAMANISHI Hirokuni; ITO Tetsuo
    Journal of Smart Processing Smart Processing Society for Materials, Environment & Energy (High Temperature Society of Japan) 4 (6) 303 - 306 2186-702X 2015 [Refereed]
     
      The removal of radioactive cesium from water solutions with some concrete blocks was investigated. When the concrete blocks were prepared by mixing zeolites, the ability of holding and transmitting water was greatly increased. The cesium ions were adsorbed to a certain extent in these concrete blocks. Moreover, when the mixtures of zeolite and metal ferrocyanide were used, the radioactive cesium could be highly removed. In particular, the residual rate of cobalt ferrocyanide was attained to 90% or above.
  • ISHIWATA Shunji; TAGA Atsushi; OGATA Fumihiko; KITAKOUJI Manabu; OUCHI Hidekazu; YAMANISHI Hirokuni; INAGAKI Masayo
    Journal of Smart Processing Smart Processing Society for Materials, Environment & Energy (High Temperature Society of Japan) 4 (6) 294 - 297 2186-702X 2015 [Refereed]
     
      Radioactive cesium has strongly bound soil as time proceeded, which could not be cleaved in mild condition. We have found that serial treatment of ammonium citrate solution and ionic liquid removed radioactive cesium from soil effectively. The sequence of the treatment is crucial, since inverse serial treatment or mixture of two kinds of solution did not show such an effect, which suggested that ammonium citrate unlocked trapped cesium in soil and ionic liquid solved it. We also found that repeating serial treatment and prolonged treatment time additively removed cesium from soil.
  • Local mat-forming cyanobacteria effectively facilitate decontamination of radioactive cesium in rice fields
    A. Yamamoto; S. Yoshida; H. Okumura; M. Inagaki; M. Furukawa; H. Yamanishi; T. Ito
    Journal of smart processing 4 (6) 287 - 293 2015 [Refereed]
  • H. Okumura; A. Yamamoto; M. Inagaki; H. Yamanishi; T. Ito
    Journal of smart processing 4 (6) 280 - 286 2015 [Refereed]
  • Study on radioactive cesium in wild mushroom
    M. Inagaki; H. Yamanishi; G. Wakabayashi; S. Hohara; T. Ito; N.Shirasaka; E. Tanesaka; M. Furukawa
    Journal of smart processing 4 (6) 275 - 279 2015 [Refereed]
  • A study of environmental radioactive cesium due to the accident of TEPCO Fukushima Daiichi NPP in Kawamata-machi, Fukushima-ken
    H. Yamanishi; M. Inagaki; G. Wakabayashi; S. Hohara; T. Ito; N. Tanaka; S. Ishiwata; A. Taga; F. Ogata; A. Horibata; T. Suzuki; M. Furukawa
    Journal of smart processing 4 (6) 268 - 274 2015 [Refereed]
  • Hiroshi Yoshii; Kouta Yanagihara; Hitoshi Imaseki; Tsuyoshi Hamano; Hirokuni Yamanishi; Masayo Inagaki; Yasuhiro Sakai; Nobuyuki Sugiura; Osamu Kurihara; Kazuo Sakai
    PLOS ONE PUBLIC LIBRARY SCIENCE 9 (7) 1932-6203 2014/07 [Refereed]
     
    Workers decommissioning the Fukushima-Daiichi nuclear power plant damaged from the Great East Japan Earthquake and resulting tsunami are at risk of injury with possible contamination from radioactive heavy atoms including actinides, such as plutonium. We propose a new methodology for on-site and rapid evaluation of heavy-atom contamination in wounds using a portable X-ray fluorescence (XRF) device. In the present study, stable lead was used as the model contaminant substitute for radioactive heavy atoms. First, the wound model was developed by placing a liquid blood phantom on an epoxy resin wound phantom contaminated with lead. Next, the correlation between the concentration of contaminant and the XRF peak intensity was formulated considering the thickness of blood exiting the wound. Methods to determine the minimum detection limit (MDL) of contaminants at any maximal equivalent dose to the wound by XRF measurement were also established. For example, in this system, at a maximal equivalent dose of 16.5 mSv to the wound and blood thickness of 0.5 mm, the MDL value for lead was 1.2 ppm (3.1 nmol). The radioactivity of Pu-239 corresponding to 3.1 nmol is 1.7 kBq, which is lower than the radioactivity of Pu-239 contaminating puncture wounds in previous severe accidents. In conclusion, the established methodology could be beneficial for future development of a method to evaluate plutonium contamination in wounds. Highlights: Methodology for evaluation of heavy-atom contamination in a wound was established. A portable Xray fluorescence device enables on-site, rapid and direct evaluation. This method is expected to be used for evaluation of plutonium contamination in wounds.
  • Sin-Ya Hohara; Masayo Inagaki; Hirokuni Yamanishi; Genichiro Wakabayashi; Wataru Sugiyama; Tetsuo Itoh
    Radiation Monitoring and Dose Estimation of the Fukushima Nuclear Accident Springer Japan 103 - 113 2014/01 [Refereed]
     
    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.
  • HOHARA Sin-ya; HOSONO Makoto; INAGAKI Masayo; IM Sung-Woon; MORIMOTO Hideo; HANAOKA Kohei; SAKAGUCHI Kenta; YAMANISHI Hirokuni; ITOH Tetsuo
    RADIOISOTOPES 公益社団法人 日本アイソトープ協会 62 (9) 659 - 665 0033-8303 2013/09 [Refereed]
     
    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.
  • WAKABAYASHI GEN'ICHIRO; YAMANISHI HIROKUNI; HOHARA SHIN'YA; INAGAKI MASAYO; ITO TETSUO; HORIGUCHI TETSUO; KOJIMA KIYOSHI; SUGIURA NOBUYUKI; FURUKAWA MICHIO
    放射線 応用物理学会放射線分科会 38 (4) 155 - 158 0285-3604 2013/07
  • YAMANISHI Hirokuni; HOHARA Sin-ya; WAKABAYASHI Genichiro; INAGAKI Masayo; HORIGUCHT Tetsuo; KOJIMA Kiyoshi; NOMA Hiroshi; SUGIURA Nobuyuki; FURUKAWA Michio; ITOH Tetsuo
    RADIOISOTOPES Japan Radioisotope Association 62 (5) 259 - 268 0033-8303 2013 [Refereed]
     
    Large amount of radioactive materials had released by the nuclear power plant accident at Fukushima Daiichi site. The level of radiation dose rate has been raised by the radioactive material on the ground. We measured the dose rates in Kawamata-machi, Fukushima Prefecture, Japan, which is located about 40km from the power plant in north-west direction. We measured the 137Cs concentration in soil samples by the Ge diode detector. The result shows more than 90% of 137Cs exists the depth from the surface to 10mm. The soil of shallow depth was sieved to 6 series by particle size. The radioactivity of the parts less than 0.5mm diameter accounts for more than 80% of the total.
  • 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 49 - 52 2012 [Refereed]
  • 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 American Nuclear Society 60 (4) 1300 - 1303 1536-1055 2011/11 [Refereed]
     
    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.
  • Hirokuni Yamanishi
    FUSION SCIENCE AND TECHNOLOGY AMER NUCLEAR SOC 60 (3) 1033 - 1036 1536-1055 2011/10 [Refereed]
     
    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.
  • Sin-Ya Hohara; Masayo Inagaki; Kiyoshi Kojima; Hirokuni Yamanishi; Genichiro Wakabayashi; Wataru Sugiyama; Tetsuo Itoh
    Transactions of the Atomic Energy Society of Japan Atomic Energy Society of Japan 10 (3) 145 - 148 1347-2879 2011/09 [Refereed]
     
    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.
  • Hirokuni Yamanishi
    RADIATION PROTECTION DOSIMETRY OXFORD UNIV PRESS 146 (1-3) 126 - 128 0144-8420 2011/07 [Refereed]
     
    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.
  • Naoto Nishio; Atsushi Yamazaki; Kenichi Watanabe; Akira Uritani; Mitsutaka Isobe; Hirokuni Yamanishi
    Plasma and Fusion Research 6 (1 SPECIAL ISSUE) 1880-6821 2011 [Refereed]
     
    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.
  • 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 1 505 - 508 2011 [Refereed]
  • S. H. Bhuiya; H. Yamanishi; T. Uda
    RADIATION MEASUREMENTS PERGAMON-ELSEVIER SCIENCE LTD 45 (10) 1096 - 1102 1350-4487 2010/12 [Refereed]
     
    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.
  • 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 81 (10) 0034-6748 2010/10 [Refereed]
     
    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.
  • N. Nishio; S. Yamamoto; K. Watanabe; A. Uritani; M. Isobe; H. Yamanishi
    Review of Scientific Instruments 81 (10) 0034-6748 2010/10 [Refereed]
     
    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.
  • S. H. Bhuiya; H. Yamanishi; T. Uda
    RADIATION PROTECTION DOSIMETRY OXFORD UNIV PRESS 141 (3) 217 - 221 0144-8420 2010/10 [Refereed]
     
    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.
  • YAMANISHI Hirokuni; SUGIURA Nobuyuki
    Japanese Journal of Health Physics Japan Health Physics Society 44 (3) 304 - 312 0367-6110 2009/09 [Refereed]
     
    The scanning method with GM survey meter is useful for detection of surface radiological density. The detection ability is varied with several parameters; those are the distance between the sample and the window of GM tube, the scanning speed and the background dose rates. We made an experimental system. In that system, a radiation source can be moved at any constant velocity with a linear scanning device. The obtained data shows that the change of count rate has some patterns due to each scanning velocity. The count rate increased with the source coming closer, and decreased with the source moving away. The maximum count rate under the scanning condition, those are 5 mm distance and 50 mm/s scanning velocity, point source on a stainless steel plate was 23% of the count rate on the fixed source. The detection ability in various scanning conditions was evaluated from the measured data. As a result, it was confirmed to be able surely to detect the lower level of the surface radiological density limit by means of the scanning condition applied to the routine work, 5 mm distance and 50 mm/s scanning velocity.
  • Sariful Haque Bhuiya; Hirokuni Yamanishi; Tatsuhiko Uda
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT ELSEVIER SCIENCE BV 607 (3) 629 - 633 0168-9002 2009/08 [Refereed]
     
    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.
  • YAMANISHI Hirokuni; MIYAKE Hitoshi; NAKAYOSHI Hisao
    RADIOISOTOPES Japan Radioisotope Association 58 (9) 611 - 615 0033-8303 2009 [Refereed]
     
    The radiation doses measured by Electric Personal Dosimeter (EPD) were compared with those by Radio-Photoluminescence Dosimeter (RPLD) in natural radiation environment. These two values were almost agreed and have a linear relationship with high correlation. However, the dose by EPD was higher than that by RPLD. The regression expression shows that the slope is a little higher than one, and this line does not pass through the zero dose point. In order to investigate the cause, the gamma ray irradiation was conducted. The result shows that the sensitivity of the EPDs were 4-11% higher than the expected dose. On the other hand, the dose rates varied from 0.019μSv/h to 0.028μSv/h in the lead box which has 10cm thickness. As a result, it would be necessary that the sensitivity of each EPD is calibrated in order to obtain an accurate dose.
  • 表面汚染密度測定における走査条件と検出能力との関係
    山西弘城; 杉浦紳之
    保健物理 44 (3) 306 - 314 2009 [Refereed]
  • Activation Analysis for LHD Experiments with Deuterium Gases
    Kiyohiko NISHIMURA; Hirokuni YAMANISHI; Katsumi HAYASHI; Akio KOMORI
    Plasma and Fusion Research 3 S1024  2008/01 [Refereed]
  • Shoji Miki; Shibao Yukinobu; Yanada Tetsuo; Shibamoto Yuji; Yamanishi Hirokuni; Honoki Hiroshi; Nakajima Tomoko; Kondo Takashi; Tsuda Masaaki
    Japanese Journal of Radiation Safety Management JAPANESE SOCIETY OF RADIATION SAFETY MANAGEMENT 5 (1) 54 - 60 1347-1503 2006 [Refereed]
     
    A portable monitoring system of airborne radioactive materials was developed for sequential monitoring of many workrooms. The system consisted of a room dust monitor detectable for the particulates emitting beta rays with its maximum energy higher than 0.15 MeV and a personal computer connected with a multichannel interface. The characteristics of background activity resulted from airborne radon progeny were investigated. The background activity in a well ventilated workroom was relatively low and equilibrated in 3-4 h after the start of sampling. Moreover, it was affected by the change of atmospheric pressure. The minimum detectable activity for 32P with the system was estimated to be 2.3×10-5 Bq cm-3 for 10 min measurement, which was less than 1/10 of the limit of airborne radioactivity concentration. The system is suggested to be more suitable than the conventional methods for the monitoring of airborne radioactive materials in the working environment.
  • H. Yamanishi
    Radioisotopes 日本アイソトープ協会 55 (7) 385 - 389 0033-8303 2006 [Refereed]
  • H Yamanishi
    NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION A-ACCELERATORS SPECTROMETERS DETECTORS AND ASSOCIATED EQUIPMENT ELSEVIER SCIENCE BV 544 (3) 643 - 648 0168-9002 2005/06 [Refereed]
     
    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.
  • Y. Fujikawa; M. Fukui; T. Baba; T. Yoshimoto; E. Ikeda; M. Saito; H. Yamanishi; T. Uda
    International Congress Series Elsevier BV 1276 415 - 417 0531-5131 2005/02 
    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.
  • YAMANISHI Hirokuni
    Japanese Journal of Health Physics Japan Health Physics Society 40 (4) 372 - 375 0367-6110 2005 [Refereed]
     
    An electronic dosimeter can be substituted for thermoluminescent dosimeters (TLDs) and radiophoto-luminescence glass dosimeters (RLPDs) in environmental radiation measurements. The dosimeter used here can record the time variation of the dose. Not only the integrated dose, but also the change of the dose rate can be grasped by means of the dosimeter. The measurement error of the dosimeters was examined. The instrumental error is small, being less than 4%. The systematic sensitivity difference was not recognized. The measurement error of 1μSv, which is the minimum dose for unit recording, was around 9%. At an integrated dose of 15μSv, the measurement error was less than 5%. Therefore, highly precise radiation monitoring is possible without checking individual sensitivity. The lower limit dose for detection, which can judge whether the dose exceeds the background, was 0.21μSv through integrating 1μSv. When irradiation was conducted at 1.05μSv/h for 2h, the data was obtained for an approximate time of irradiation as well as the total dose. The dosimeter is suitable for radiation monitoring around X-ray generators or accelerators, where radiation is generated intermittently.
  • KOGANEZAWA Takayuki; IIDA Takao; OGATA Yoshimune; TSUJI Naruhito; KAKIUCHI Masahisa; SATAKE Hiroshi; YAMANISHI Hirokuni; SAKUMA Yoichi
    Radioisotopes 日本アイソトープ協会 53 (5) 277 - 285 0033-8303 2004/05 [Refereed]
  • Hirokuni Yamanishi; Yoichi Sakuma; Naofumi Yamamura; Hiroo Sato; Kohtaro Ueki
    Journal of Nuclear Science and Technology 41 392 - 394 0022-3131 2004/03 [Refereed]
     
    A neutron monitor for measuring dose of three energy groups is being developed. The radiation quality factors that ICRP recommends differ among neutron energies. In order to evaluate neutron dose precisely, it is expected that the neutron fluence of each energy group should be measured. Therefore, we propose a measuring instrument with a three-layer configuration. A liquid scintillator (LS) is arranged at the center, while Li-6 glass scintillators (GS) are arranged in an external layer and interposed layer. Fast neutrons are detected by the LS, and low energy neutrons are measured by the GS of the outer layer. Other middle energy neutrons are measured by the GS of the inner layer. The configuration of external layer and interposed layer was discussed using MCNP. Boron nitride was placed as a neutron absorption material between the external layer and intermediate layer. As a result of this design, the outer and inner GS can measure low energy neutrons in the range of thermal neutrons to 10"2 MeV, and middle energy neutrons from 10x−2 to 1 MeV, respectively. © 2014 Atomic Energy Society of Japan.
  • H.Yamanishi; H.Miyake; T.Yamasaki; K.Komura
    Japanese Journal of Health Physics Japan Health Physics Society 39 (2) 108 - 112 0367-6110 2004 [Refereed]
  • K. Shinotsuka; H. Yamanishi; Y. Sakuma; M. Tanaka; N. Tsuji; T. Uda
    Journal of Radioanalytical and Nuclear Chemistry 258 (2) 233 - 241 0236-5731 2003/11 [Refereed]
     
    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.
  • YAMANISHI Hirokuni
    Japanese Journal of Health Physics Japan Health Physics Society 38 (3) 267 - 269 0367-6110 2003/09 [Refereed]
  • 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 ELSEVIER SCIENCE BV 501 (2-3) 589 - 593 0168-9002 2003/04 [Refereed]
     
    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.
  • Y Sakuma; Y Ogata; N Tsuji; H Yamanishi; T Iida
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY SPRINGER 255 (2) 325 - 327 0236-5731 2003 [Refereed]
     
    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.
  • Hirokuni YAMANISHI; Hitoshi MIYAKE
    Journal of Nuclear Science and Technology Informa UK Limited 40 (1) 44 - 48 0022-3131 2003/01 [Refereed]
     
    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. © 2003 Taylor & Francis Group, Ltd.
  • Hirokuni YAMANISHI; Hitoshi MIYAKE; Keisuke MATSUOKA; Mitsutaka ISOBE
    Japanese Journal of Health Physics Japan Health Physics Society 38 (3) 239 - 242 0367-6110 2003 [Refereed]
  • H. Yamanishi; H.Miyake; T.Yamasaki; K.Komura
    Japanese Journal of Health Physics Japan Health Physics Society 38 (1) 45 - 49 0367-6110 2003 [Refereed]
  • Hirokuni YAMANISHI; Yoichi SAKUMA; Haruo OBAYASHI
    RADIOISOTOPES Japan Radioisotope Association 52 (5) 235 - 241 0033-8303 2003 [Refereed]
  • Yoko Fujikawa; Kiyoshi Shizuma; Emi Ikeda; Takahiro Baba; Takaaki Yoshimoto; Masami Fukui; Masahiro Saito; Hirokuni Yamanishi; Tatsuhiko Uda
    Journal of Nuclear Science and Technology 39 564 - 567 0022-3131 2002/11 [Refereed]
     
    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.
  • Hirokuni Yamanishi; Satarou Yamaguchi; Takayuki Yamaguchi; Kohtaro Ueki
    Transactions of the Atomic Energy Society of Japan 日本原子力学会 1 (1) 15 - 19 1347-2879 2002 [Refereed]
     
    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.
  • 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 AMER NUCLEAR SOCIETY 39 (2) 753 - 757 0748-1896 2001/03 [Refereed]
     
    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.
  • Hirokuni YAMANISHI; Hitoshi MIYAKE; Tadashi YAMASAKI; Kazuhisa KOMURA
    RADIOISOTOPES Japan Radioisotope Association 50 (9) 419 - 423 0033-8303 2001 [Refereed]
  • H Yamanishi; H Miyake; T Uda; S Tanahashi; M Saitou; H Handa
    FUSION ENGINEERING AND DESIGN ELSEVIER SCIENCE SA 51-52 647 - 652 0920-3796 2000/11 [Refereed]
     
    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.
  • 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 ELSEVIER SCIENCE SA 49-50 661 - 666 0920-3796 2000/11 [Refereed]
     
    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.
  • H Handa; M Saitou; K Hayashi; H Yamanishi; K Nishimura; H Yamada; O Motojima; K Yamada; S Kamogawa
    FUSION ENGINEERING AND DESIGN ELSEVIER SCIENCE SA 43 (1) 59 - 74 0920-3796 1998/10 [Refereed]
     
    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.
  • H Yamanishi; A Sagara; O Motojima; T Noda; S Tanaka; T Terai; T Uda; FFHR Group
    Fusion Engineering and Design Elsevier BV 41 (1-4) 583 - 588 0920-3796 1998/09 [Refereed]
  • 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 ELSEVIER SCIENCE BV 248 147 - 152 0022-3115 1997/09 [Refereed]
     
    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.
  • T Uda; H Yamanishi; H Miyake; J Kodaira; Y Sakuma; H Hirabayashi; H Obayashi; H Yamada; O Motojima
    JOURNAL OF FUSION ENERGY PLENUM PUBL CORP 16 (1-2) 167 - 173 0164-0313 1997/06 [Refereed]
     
    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.
  • A. Sagara; O. Motojima; K. Watanabe; S. Imagawa; H. Yamanishi; O. Mitarai; T. Satow; H. Tikaraishi
    Fusion Engineering and Design 29 (C) 51 - 56 0920-3796 1995/03 [Refereed]
     
    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.
  • H HANDA; K HAYASHI; H YAMANISHI; Y SAKUMA; H KANEKO; H OBAYASHI; O MOTOJIMA; Y OGAWA; K YAMADA; T ABE
    FUSION ENGINEERING AND DESIGN ELSEVIER SCIENCE SA 28 (1/4) 515 - 524 0920-3796 1995/03 [Refereed]
     
    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.
  • M. Osakabe; J. Fujita; J. Kodaira; M. Sasao; H. Yamanishi; S. Itoh; M. D. Diesso; L. C. Johnson; A. L. Roquemore
    Review of Scientific Instruments 66 (1) 920 - 922 0034-6748 1995 [Refereed]
     
    A ΔE-E type proton recoil telescope, called COTETRA, was developed and is presently being applied to TFTR D-T fusion experiments. Two types of COTETRA were prepared for this experiment. One set is used primarily for high-resolution measurements of the neutron energy and uses Si diode as an E detector (set A), while another set (set B) uses a plastic scintillator to attain high count-rate capability. Both sets of COTETRA have small physical dimensions and use fast NIM electronic modules for high neutron flux rate measurements. A data acquisition system has been developed for the TFTR CAMAC system. A calibration experiment has been performed using a D-T neutron generator. Energy resolution of 4.0% is obtained for set A. Set B is expected to work at a count rate of up to 104 cps, which corresponds to a neutron flux rate of ∼109 (n/cm2)/s at the detector position. Currently, both of them are installed under the multichannel neutron collimator of TFTR. © 1995 American Institute of Physics.
  • Radiation monitoring system developed for fusion site in Toki
    H.Obayashi; J.Kodaira; Y.Sakuma; H.Yamanishi; H.Miyake
    Fusion Technology 1994 1421 - 1424 1995
  • SAKUMA Yoichi; YAMANISHI Hirokuni; KODAIRA Junichi; OBAYASHI Haruo; KANETA Hidehiko; TEZUKA Machiko
    Jpn. J. Health Phys. Japan Health Physics Society 30 (2) 127 - 132 0367-6110 1995 [Refereed]
     
    We planned to synthesize tritium-free water from natural gas which is presumed to contain no tritium. In the liquid scintillation counting method, tritium-free water is used to compensate for the background counts. To synthesize tritium-free water, we assembled an apparatus which is capable of oxidizing natural gas into water under conditions completely isolated from the environment. As previously reported, the quality of the water depends mainly on the material oxygen used. We synthesized water using conventional electrolyzed pure oxygen. Analysis by the electrolytic enrichment technique showed that there was almost no tritium in the synthesized water.
  • AKHMAD Yus R.; IKEBE Yukimasa; SHIMO Michikuni; IIDA Takao; OBAYASHI Haruo; SAKUMA Youichi; YAMANISHI Hirokuni; KODAIRA Jun-ichi
    Jpn. J. Health Phys. Japan Health Physics Society 29 (4) 399 - 409 0367-6110 1994 [Refereed]
     
    By using Pb shield of 10cm thick, new methods were developed to estimate each components of environmental radiation doses measured with CaSO4: Tm thermoluminescence dosemeter (TLD-UD 200S). These methods aimed at estimating the air absorbed dose increment due to radioactive materials in the atmosphere or downward radiations released from nuclear facilities. As a preliminary step for the application to detect small dose increments, TLDs preirradiated by 2.2, 3.6 and 7.2μGy with a 60Co source were placed at a location of which background level was 55.5nGyh-1. Performance of the TLD system seems to be satisfactory for the practical use since discrepancy between estimated and given doses was less than 30% for a given dose increment of 7.2μGy. The responses of the TLDs to cosmic and natural gamma radiations were also investigated with various dosimetric methods. It was found that the responses of the TLDs to natural gamma radiations are in agreement with those inferred from other methods, but their responses to cosmic radiation were definitely lower.
  • Y IKEBE; H YAMANISHI; K TOJO; T IIDA
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN ATOMIC ENERGY SOC JAPAN 35 (8) 735 - 738 0004-7120 1993/08 [Refereed]
  • H YAMANISHI; Y IKEBE; T IIDA
    JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN ATOMIC ENERGY SOC JAPAN 35 (4) 329 - 337 0004-7120 1993/04 [Refereed]
     
    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.
  • H YAMANISHI; T IIDA; Y IKEBE; S ABE; T HATA
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY TAYLOR & FRANCIS LTD 28 (4) 331 - 338 0022-3131 1991/04 [Refereed]
     
    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.
  • JIN Yihe; IKEBE Yukimasa; IIDA Takao; SHIMO Michikuni; YAMANISHI Hirokuni; GUO Qiuju; ABE Siro; WANG Zuoyuan; REN Tianshan; TIAN Deyuan; HE Zhijian; FAN Xin; XIE Hongru; YANG Xiaotong; LI Suozhao; LU Shaoxiang; ZHANG Haoran; DU Kairu
    Jpn. J. Health Phys. Japan Health Physics Society 26 (4) 341 - 349 0367-6110 1991 [Refereed]
     
    Measurements of 222Rn in outdoor air and indoor air have been carried out every 2 months during about one year from Nov. 1988 using passive electrostatic integrating 222Rn monitor developed by Iida et al. The annual mean outdoor 222Rn concentrations at Beijing, Xi'an, Nanjing, Shanghai, Fuzhou and Guiyang were 8.0, 11.2, 6.4, 4.8, 9.5 and 12.2Bq·m-3, respectively. The high outdoor 222Rn levels at Beijing and Xi'an, situated in inland area, may be attributed to high frequency of the occurrence of inversions in winter. The low 222Rn levels at Nanjing and Shanghai and the high 222Rn levels at Fuzhou and Guiyang correspond to their geological conditions and the 226Ra concentrations in soil. The annual mean indoor 222Rn concentrations were about 2-3 fold of outdoor concentrations at every city. The average indoor 222Rn concentration in China was 29.2Bq·m-3. The annual effective dose equivalent resulting from outdoor and indoor 222Rn concentrations amounts to about 0.72mSv·y-1.
  • Takao Iida; Yukimasa Ikebe; Takatoshi Hattori; Hirokuni Yamanishi; Siro Abe; Kiyoshi Ochifuji; Shintaro Yokoyama
    Health Physics 54 (2) 139 - 148 0017-9078 1988/02 [Refereed]
     
    This paper describes a new type of electrostatic integrating 222Rn monitor designed for the environmental 222Rn monitoring. The window area of the monitor was selected to make the exchange rate optimal. The collecting electrode was positioned on the basis of calculating the internal electric field. A drying agent, P2O5, was placed in the bottom of the monitor, since the collection efficiency of 218Po+ atoms depends on the humidity of the air. The monitors have been calibrated against known 222Rn exposures. The detection limit is 1.2 Bq m−3 for an exposure time of 2 mo. In a small survey, annual mean 222Rn concentrations between 3.7 and 9.5 Bq m−3 in outdoor air and between 6.4 and 11.9 Bq m−3 in indoor air were measured. © 1988 Health Physics Society.

Books etc

  • 杉浦, 紳之; 鈴木, 崇彦; 山西, 弘城 (Joint work)通商産業研究社 2017/02 9784860450984 165p

Conference Activities & Talks

  • Development of neutron detector using plastic scintillator for detection of nuclear/radioactive material
    持丸貴則; 高橋時音; 小泉光生; 弘中浩太; 加藤圭吾; 山西弘城; 若林源一郎
    日本原子力学会春の年会予稿集(CD-ROM)  2022
  • Development of neutron dose detector with three-layer structure  [Not invited]
    H. Yamanishi
    日本保健物理学会第５３回研究発表会  2020/06
  • Analysis of Fluctuation Factors of Radon Concentration in a Reactor Facility
    吉澤祐哉; 山西弘城; 稲垣昌代
    日本放射線安全管理学会学術大会講演予稿集  2020
  • Development of Source Direction Detector for Nuclear Security
    篠原慎吾; 山西弘城
    日本放射線安全管理学会学術大会講演予稿集  2020
  • Development of neutron measurement training program using an alpha ray survey meter for radiation protection education
    矢野太盛; 山西弘城
    日本放射線安全管理学会学術大会講演予稿集  2020
  • Monitoring technique for detection of nuclear and radioactive materials on major public events (1) Development of wide area monitoring system
    高橋時音; 小泉光生; 富川裕文; 木村祥紀; 佐藤優樹; 寺阪祐太; 鳥居建男; 山西弘城; 若林源一郎
    日本原子力学会秋の大会予稿集(CD-ROM)  2020
  • Evaluation of radioactive cesium behavior in Mushroom mycelium by tracer experiment
    西小野華乃子; 坂本文徳; 香西直文; 山西弘城
    日本放射線安全管理学会学術大会講演予稿集  2019
  • 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(Web)  2018
  • 九州地域における温泉水中のラドン濃度分布 II
    稲垣昌代; 山西弘城; 古賀妙子; 森嶋彌重
    日本保健物理学会研究発表会講演要旨集  2017
  • Survey and decontamination of radium-223 dichloride for alpha-particle radionuclide therapy in clinical facilities  [Not invited]
    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  2016/10  SPRINGER
  • きのこへの放射性セシウム移行の栽培による評価  [Not invited]
    山西弘城; 稲垣昌代; 種坂英次; 白坂憲章
    日本保健物理学会第49回研究発表会  2016/06
  • バイオコークス技術を用いた震災除染物の減容化
    大橋憲; 笹内謙一; 井田民男; 水野諭; 山西弘城
    日本実験力学会講演論文集  2016
  • 福島県における小規模農業用ため池の放射性Cs除染
    奥村博司; 松野裕; 山本純之; 稲垣昌代; 山西弘城; 伊藤哲夫
    農業農村工学会大会講演会講演要旨集(CD-ROM)  2016
  • 近畿大学原子炉の再稼働に向けた現状
    芳原新也; 杉山亘; 左近敦士; 橋本憲吾; 山西弘城; 若林源一郎; 伊藤哲夫
    日本原子力学会秋の大会予稿集(CD-ROM)  2016
  • 韓国の教育訓練用原子炉を用いた原子力人材育成
    若林源一郎; 橋本憲吾; 伊藤哲夫; 山西弘城; 芳原新也; 稲垣昌代; KIM Myung-Hyun
    日本原子力学会春の年会予稿集(CD-ROM)  2016
  • 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  [Not invited]
    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
    日本保健物理学会第48回研究発表会  2015/07
  • Migration of radioactive cesium to water from grass and fallen leaves  [Not invited]
    H.Yamanishi; M.Inagaki; G.Wakabayashi; S.Hohara; T.Itoh; M.Furukawa
    International Symposium on Radiological Issues for Fukushima’s Revitalized Future  2015/05
  • 野生きのこに含まれる放射性セシウムの調査
    稲垣昌代; 山西弘城; 若林源一郎; 芳原新也; 伊藤哲夫; 白坂憲章; 種坂英次; 古川道郎
    スマートプロセス学会総合学術講演会講演概要  2015
  • 福島県の小規模ため池における放射性Csの汚染メカニズムに関する考察
    奥村博司; 山本純之; 稲垣昌代; 山西弘城; 伊藤哲夫
    日本雨水資源化システム学会研究発表会講演要旨集  2015
  • 福島県川俣町における近畿大学の活動 環境中放射性Csの現状調査と除染・吸着回収並びに廃棄物減容
    伊藤哲夫; 山西弘城; 古川道郎
    スマートプロセス学会総合学術講演会講演概要  2015
  • バイオコークス技術を用いた震災防除物の減容化
    大橋憲; 笹内謙一; 井田民男; 水野諭; 山西弘城
    スマートプロセス学会総合学術講演会講演概要  2015
  • 近畿大学原子炉に対する新規制基準適合確認の現状
    芳原新也; 杉山亘; 橋本憲吾; 山西弘城; 若林源一郎; 松田外志朗; 堀口哲男; 伊藤眞; 伊藤哲夫
    日本原子力学会秋の大会予稿集(CD-ROM)  2015
  • Survey of Environmental Radiation in Kawamata-machi, Fukushima-ken ～Measurement of radioactive cesium in soil and plant～  [Not invited]
    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  [Not invited]
    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
  • 草や落葉に含有される放射性Csの水への溶出  [Not invited]
    山西弘城; 稲垣昌代; 若林源一郎; 芳原新也; 伊藤哲夫; 古川道郎
    日本保健物理学会第47回研究発表会  2014/06
  • 汚染バイオマスのバイオコークス技術による再生可能エネルギー備蓄に関する研究
    井田民男; 水野諭; 山西弘城; 大橋憲; 谷口美希; 笹内謙一
    日本機械学会年次大会講演論文集(CD-ROM)  2014
  • 福島県で採取した野生きのこに含まれる放射性セシウム濃度
    稲垣昌代; 山西弘城; 若林源一郎; 芳原新也; 伊藤哲夫; 種坂英次; 白坂憲章; 古川道郎
    日本保健物理学会研究発表会講演要旨集  2014
  • 蛍光X線分析による創傷部重金属汚染評価法の検討
    吉井裕; 柳原孝太; 伊豆本幸恵; 今関等; 濱野毅; 栗原治; 酒井一夫; 栗野嗣史; 酒井康弘; 山西弘城; 稲垣昌代
    日本原子力学会春の年会予稿集(CD-ROM)  2014
  • 重金属汚染創傷部模擬ファントムの構築とその蛍光X線分析による評価
    柳原孝太; 柳原孝太; 吉井裕; 伊豆本幸恵; 松山嗣史; 松山嗣史; 今関等; 濱野毅; 山西弘城; 稲垣昌代; 酒井康弘; 栗原治; 酒井一夫
    X線分析討論会講演要旨集  2014
  • 蛍光X線分析による創傷部汚染迅速評価(1)拭き取り法における手法の最適化
    伊豆本幸恵; 吉井裕; 柳原孝太; 松山嗣史; 今関等; 濱野毅; 栗原治; 酒井一夫; 山西弘城; 稲垣昌代; 右田豊紀恵; 酒井康弘
    日本原子力学会秋の大会予稿集(CD-ROM)  2014
  • 重金属汚染創傷部の拭き取りを想定した汚染血液の蛍光X線分析による評価
    吉井裕; 伊豆本幸恵; 柳原孝太; 柳原孝太; 松山嗣史; 松山嗣史; 今関等; 濱野毅; 山西弘城; 稲垣昌代; 酒井康弘; 栗原治; 酒井一夫
    X線分析討論会講演要旨集  2014
  • 蛍光X線分析による創傷部汚染迅速評価(2)模擬血液による傷モデルファントムの保存性向上
    松山嗣史; 吉井裕; 伊豆本幸恵; 柳原孝太; 今関等; 濱野毅; 栗原治; 酒井一夫; 右田豊紀恵; 酒井康弘; 山西弘城; 稲垣昌代
    日本原子力学会秋の大会予稿集(CD-ROM)  2014
  • 福島における小規模農業用ため池のCs汚染とその除去
    奥村博司; 山本純之; 稲垣昌代; 山西弘城; 伊藤哲夫
    日本雨水資源化システム学会研究発表会講演要旨集  2014
  • 市販サーベイメータの223Ra薬剤に対する応答調査
    芳原新也; 稲垣昌代; 細野眞; 山西弘城; 伊藤哲夫
    日本原子力学会秋の大会予稿集(CD-ROM)  2014
  • 近畿大学における原子力人材育成事業の現状
    若林源一郎; 橋本憲吾; 伊藤哲夫; 山西弘城; 芳原新也; 堀口哲男; 杉山亘; 伊藤眞; 松田外志朗; 稲垣昌代; 山本友完
    日本原子力学会秋の大会予稿集(CD-ROM)  2014
  • 近畿大学原子炉を用いた教員向け原子炉実験研修会
    若林源一郎; 芳原新也; 杉山亘; 堀口哲男; 松田外志朗; 山西弘城; 橋本憲吾; 伊藤眞; 伊藤哲夫; 稲垣昌代; 山本友完
    日本原子力学会秋の大会予稿集(CD-ROM)  2014
  • 創傷部鉛汚染ファントムの蛍光X線分析
    吉井裕; 伊豆本幸恵; 柳原孝太; 松山嗣史; 柳原孝太; 松山嗣史; 今関等; 濱野毅; 山西弘城; 稲垣昌代; 酒井康弘; 栗原治; 酒井一夫
    日本保健物理学会研究発表会講演要旨集  2014
  • 可搬型および据え置き型蛍光X線分析装置を用いた血中重金属ふき取り測定法の開発
    伊豆本幸恵; 吉井裕; 柳原孝太; 松山嗣史; 柳原孝太; 松山嗣史; 今関等; 濱野毅; 山西弘城; 稲垣昌代; 酒井康弘; 栗原治; 酒井一夫
    日本保健物理学会研究発表会講演要旨集  2014
  • 福島県下における環境放射線の現状と個人線量の測定例
    山西弘城
    日本原子力学会春の年会予稿集(CD-ROM)  2014
  • 放射性汚染バイオマスの減容に係るバイオコークス技術の適用
    大橋憲; 谷口美希; 笹内謙一; 水野諭; 井田民男; 山西弘城
    バイオマス科学会議発表論文集  2014
  • 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  2013/06
  • バイオアッセイ法によるスクリーニング検査を目的とした尿中放射性セシウムの高感度測定法の検討  [Not invited]
    山西弘城; 伊藤哲夫; 杉浦紳之; 稲垣昌代; 松原昌平; 吉村共之; 窪谷英明; 加藤結花; 荻原 清
    日本保健物理学会第46回研究発表会  2013/06
  • 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  [Not invited]
    山西弘城; 稲垣昌代; 若林源一郎; 芳原新也; 伊藤哲夫; 石渡俊二; 多賀 淳; 緒方文彦; 古川道郎
    日本保健物理学会第46回研究発表会  2013/06
  • Mat-forming cyanobacteria effectively decontaminate radioactive cesium.  [Not invited]
    吉田 繁; 山西 弘城; 伊藤 哲夫; 福島県川俣町長
    日本地球惑星科学連合2013年大会  2013/05  千葉県幕張メッセ国際会議場  日本地球惑星科学連合2013年大会
  • シアノバクテリアの放射性セシウム除染能力  [Not invited]
    吉田 繁; 山西 弘城; 伊藤 哲夫; 福島県川俣町長
    第４回日本光合成学会年会：公開シンポジウム「30年後の光合成研究」  2013/05  名古屋市  第４回日本光合成学会年会：公開シンポジウム「30年後の光合成研究」
  • 土壌中放射性セシウムの溶出に関する研究,  [Not invited]
    山西弘城; 稲垣昌代; 石渡俊二; 多賀 淳; 若林源一郎; 芳原新也; 伊藤哲夫
    原子力学会2013春の年会  2013/03
  • Ihara Tatsuhiko; Itoh Tetsuo; Yamanishi Hirokuni; Wakabayashi Genichiro; Hohara Shin-ya; Inagaki Masayo
    Proceedings of AESJ  2013  Atomic Energy Society of Japan
     
    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．
  • Hohara Sin-ya; Inagaki Masayo; Yamanishi Hirokuni; Wakabayashi Genichiro; Sugiyama Wataru; Itoh Tetsuo
    Proceedings of AESJ  2013  Atomic Energy Society of Japan
     
    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。
  • 福島県川俣町山木屋地区における野生きのこの放射性セシウム濃度
    稲垣昌代; 山西弘城; 若林源一郎; 芳原新也; 伊藤哲夫; 白坂憲章; 種坂英次; 奥村博司; 古川道郎
    日本菌学会大会講演要旨集  2013
  • 蛍光X線分析による創傷部鉛体表面汚染評価
    吉井裕; 今関等; 濱野毅; 鈴木敏和; 田嶋克史; 杉浦紳之; 柳原孝太; 酒井康弘; 山西弘城; 稲垣昌代
    日本原子力学会春の年会予稿集(CD-ROM)  2013
  • 創傷部アクチニド汚染迅速評価を目指した蛍光X線分析法による創傷部重金属汚染分析
    吉井裕; 柳原孝太; 柳原孝太; 今関等; 濱野毅; 山西弘城; 稲垣昌代; 酒井康弘; 鈴木敏和; 栗原治; 田嶋克史; 杉浦紳之
    日本保健物理学会研究発表会講演要旨集  2013
  • オートウェルガンマカウンタを用いた尿及び環境試料中の放射性セシウム濃度の測定 2.ゲルマニウム半導体検出器との測定比較
    山西弘城; 伊藤哲夫; 杉浦伸之; 稲垣昌代; 窪谷英明; 加藤結花; 荻原清; 吉村共之
    アイソトープ・放射線研究発表会要旨集  2013
  • 低バックグラウンド液体シンチレーションカウンタを用いた尿中の放射性セシウム濃度の測定 2.ゲルマニウム半導体検出器との測定比較
    山西弘城; 伊藤哲夫; 杉浦伸之; 稲垣昌代; 加藤結花; 窪谷英明; 荻原清; 吉村共之
    アイソトープ・放射線研究発表会要旨集  2013
  • 土壌中放射性セシウムの溶出に関する研究
    山西弘城; 稲垣昌代; 石渡俊二; 多賀淳; 若林源一郎; 芳原新也; 伊藤哲夫
    日本原子力学会春の年会予稿集(CD-ROM)  2013
  • 福島県川俣町における環境放射線調査(3)~野生きのこに含まれる放射性セシウム濃度~
    稲垣昌代; 山西弘城; 若林源一郎; 芳原新也; 伊藤哲夫; 白坂憲章; 種坂英次; 奥村博司; 古川道郎
    日本保健物理学会研究発表会講演要旨集  2013
  • シアノバクテリアの放射性セシウム除染能力：ストロマトライト形成実験からの応用  [Not invited]
    吉田 繁; 山西 弘城; 伊藤 哲夫; 福島県川俣町長
    古生物学会第162回例会  2013/01  横浜国立大学  古生物学会第162回例会
  • 尿を対象にしたバイオアッセイ法による内部被ばく線量の評価  [Not invited]
    山西弘城; 伊藤哲夫; 杉浦紳之; 稲垣昌代; 松原昌平; 荻原 清; 吉村共之; 窪谷英明; 加藤結花
    原子力学会2012秋の大会  2012/09
  • 福島県川俣町における近畿大学の活動  [Not invited]
    山西 弘城
    日本保健物理学会第45回研究発表会  2012/06
  • 福島県川俣町における環境放射線調査（１）－放射性セシウムの除去と蓄積に関する研究－  [Not invited]
    山西弘城; 稲垣昌代; 若林源一郎; 芳原新也; 伊藤哲夫; 古川道郎
    日本保健物理学会第45回研究発表会  2012/06
  • Development and utilization of gamma-ray shielding suit excellent easy-to-wear  [Not invited]
    T. Itoh; H. Yamanishi; T. Yamamoto; T. Yamamoto; K. Yamamoto
    13th Intern. Congress of the International Radiation Protection Association  2012/05
  • 福島中通地区における放射性汚染調査
    芳原新也; 稲垣昌代; 山西弘城; 若林源一郎; 杉山亘; 伊藤哲夫
    日本保健物理学会研究発表会講演要旨集  2012
  • 福島県川俣町における環境放射線調査(1)放射性セシウムの除去と蓄積に関する研究
    山西弘城; 稲垣昌代; 若林源一郎; 芳原新也; 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  2012
  • 福島県川俣町における環境放射線調査(2)~表土の粒度別放射性セシウム濃度~
    稲垣昌代; 山西弘城; 若林源一郎; 芳原新也; 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  2012
  • 福島中通地区における空間線量率分布の測定
    芳原新也; 稲垣昌代; 山西弘城; 若林源一郎; 杉山亘; 伊藤哲夫
    応用物理学会学術講演会講演予稿集(CD-ROM)  2012
  • 放射性セシウムの土壌への沈着状況の分析  [Not invited]
    山西弘城; 伊藤哲夫; 古川道郎; 杉浦紳之; 若林源一郎; 芳原新也; 堀口哲男; 稲垣昌代; 小島 清
    日本保健物理学会第44回研究発表会  2011/10
  • 電子式線量計による長期間連続の環境放射線線量測定  [Not invited]
    山西弘城; 三宅 均; 中吉久雄
    日本保健物理学会第44回研究発表会  2011/10
  • 福島県川俣町における環境放射線調査(1)調査の概要と土壌中の放射性物質  [Not invited]
    伊藤哲夫; 山西弘城; 杉浦紳之; 若林源一郎; 堀口哲男; 芳原新也; 稲垣昌代; 小島 清; 村田祥之; 古川道郎
    日本原子力学会2011年秋の大会  2011/09
  • 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  Atomic Energy Society of Japan
     
    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。
  • HOHARA SIN-YA; Inagaki Masayo; Kojima Kiyoshi; Yamanishi Hirokuni; Wakabayashi Genichiro; Itoh Tetsuo
    Proceedings of AESJ  2011  Atomic Energy Society of Japan
     
    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。
  • Ito Tetsuo; Murata Yoshiyuki; Furukawa Michiro; Sugiura Nobuyuki; Yamanishi Hirokuni; Horiguchi Tetsuo; Hohara Shinya; Wakabayashi Genichiro; Inagaki Masayo; Kojima Kiyoshi
    Proceedings of AESJ  2011  Atomic Energy Society of Japan
     
    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。
  • 測定に関する検討
    岩岡和輝; 岩岡和輝; 飯田孝夫; 飯本武志; 石川徹夫; 石森有; 五代儀貴; 笠井篤; 北口博司; 黒澤龍平; 真田哲也; 下道国; 反町篤行; 田阪茂樹; 土居主尚; 床次眞司; 橋本周; 細田正洋; 安岡由美; 山崎敬三; 山西弘城; 柚木彰; 吉永信治; 米原英典
    日本保健物理学会研究発表会講演要旨集  2011
  • 国際機関の動向
    飯本武志; 石川徹夫; 山西弘城; 細田正洋; 笠井篤
    日本保健物理学会研究発表会講演要旨集  2011
  • ヘリカル型核融合実験装置の中性子モニタリングシステムに関する研究 その2
    西尾直人; 山崎淳; 渡辺賢一; 瓜谷章; 磯部光孝; 山西弘城
    日本原子力学会秋の大会予稿集(CD-ROM)  2011
  • ヘリカル型核融合実験装置の中性子モニタリングシステムに関する研究
    西尾直人; 山崎淳; 渡辺賢一; 瓜谷章; 磯部光孝; 山西弘城
    日本原子力学会春の年会予稿集(CD-ROM)  2011
  • 大型ヘリカル装置重水素実験における放射化環境の計算  [Not invited]
    山西弘城; 西村清彦
    第８回核融合エネルギー連合講演会  2010/06
  • LHDの中性子モニタに関する予備検討
    西尾直人; 山崎淳; 瓜谷章; 渡辺賢一; 磯部光孝; 山西弘城
    核融合エネルギー連合講演会(CD-ROM)  2010
  • 平坦応答を有する中性子モニタの開発
    大塚準平; 瓜谷章; 渡辺賢一; 西尾直人; 山崎淳; 磯部光孝; 山西弘城
    核融合エネルギー連合講演会(CD-ROM)  2010
  • ヘリカル型核融合実験装置の中性子モニタの校正に関する検討
    西尾直人; 山崎淳; 瓜谷章; 渡辺賢一; 磯部光孝; 山西弘城
    応用物理学会学術講演会講演予稿集(CD-ROM)  2010
  • 放射化物クリアランスにおけるNaIサーベイ手法の検討  [Not invited]
    山西弘城; A.Sabourov; M.Kerimbaev; J.Liu
    日本保健物理学会第43回研究発表会  2009/06
  • 土岐地区における環境中性子線の測定
    占部逸正; 佐川宏幸; 山西弘城
    日本保健物理学会研究発表会講演要旨集  2009
  • 線源の広がりに起因するサーベイメータの計数率変化  [Not invited]
    山西弘城; 杉浦紳之
    日本放射線安全管理学会第7回学術大会  2008/12
  • エネルギー依存性が極小の中性子線量測定の開発  [Not invited]
    山西弘城; ブイヤ サリフル ハック; 宇田達彦
    日本保健物理学会第4２回研究発表会  2008/06
  • 重水素プラズマから放出される中性子のエネルギースペクトル
    磯部光孝; 山西弘城; 笹尾眞實子; 長壁正樹
    プラズマ・核融合学会年会(Web)  2008
  • エネルギー依存性が極小の中性子線量測定器の開発
    山西弘城; BHUIYA Sariful Haque; 宇田達彦
    日本保健物理学会研究発表会講演要旨集  2008
  • 表面放射能密度測定における走査速度と検出能力の関係  [Not invited]
    杉浦紳之; 山西弘城
    日本原子力学会2007年春の年会,  2007/03
  • 重水素プラズマを対象とした中性子スペクトロメータとしての3He比例計数管の性能評価
    磯部光孝; 浅井啓輔; 山西弘城; 三宅均; 長壁正樹; 山内通則; 笹尾真実子
    プラズマ・核融合学会年会(Web)  2007
  • 直接法による表面汚染密度測定の標準化に関する考察
    杉浦紳之; 山西弘城
    日本保健物理学会研究発表会講演要旨集  2007
  • 表面放射能密度測定における走査条件と検出能力との関係
    杉浦紳之; 山西弘城
    日本原子力学会春の年会要旨集(CD-ROM)  2007
  • 多地点同時測定による放射線発生特性の把握  [Not invited]
    山西 弘城
    日本原子力学会「2006秋の大会」  2006/09
  • 電解濃縮を用いた環境水中トリチウム濃度測定法の効率化 (3)
    佐久間洋一; 山西弘城; 緒方良至; 飯田孝夫; 垣内正久; 佐竹洋; 鳥養祐二; 辻成人
    KEK Proceedings  2005
  • 環境水中トリチウム測定手法の簡素化 2
    佐久間洋一; 山西弘城; 緒方良至; 辻成人; 鳥養祐二
    日本原子力学会秋の大会予稿集(CD-ROM)  2005
  • TLDを検出素子とした多層型中性子線量測定器の設計(II)
    山西弘城
    日本原子力学会春の年会要旨集  2005
  • 環境水中トリチウム濃度測定の時間効率化および正確化 2
    佐久間洋一; 山西弘城; 緒方良至; 辻成人; 佐竹洋; 垣内正久; 飯田孝夫
    アイソトープ・放射線研究発表会要旨集  2005
  • TLDを検出素子とした多層型中性子線量測定器の設計(3)
    山西弘城
    日本原子力学会秋の大会予稿集(CD-ROM)  2005
  • 電解濃縮を用いた環境水中トリチウム濃度測定の時間効率化 3
    佐久間洋一; 山西弘城; 飯田孝夫; 緒方良至; 辻成人; 垣内正久; 佐竹洋; 鳥養祐二
    日本放射化学会年会・放射化学討論会研究発表要旨集  2005
  • 熱蛍光シートによる中性子線の二次元測定
    佐久間洋一; 山西弘城; 橋本光康; 佐藤博夫; 植木紘太郎; 石川雄三; 国枝悦夫; 古林徹; 義本孝明
    日本保健物理学会研究発表会講演要旨集  2004
  • 多層型エネルギー群別中性子線量測定器の開発
    山村直史; 飯田孝夫; 山根義宏; 山西弘城; 佐久間洋一; 植木紘太郎; 佐藤博夫
    日本原子力学会春の年会要旨集  2004
  • 電解濃縮を用いた環境水中トリチウム濃度測定の時間効率化 2
    佐久間洋一; 山西弘城; 飯田孝夫; 緒方良至; 辻成人; 垣内正久; 佐竹洋; 鳥養祐二
    日本放射化学会年会・放射化学討論会研究発表要旨集  2004
  • 電子式積算線量計のトレンドデータを用いた放射線監視の可能性
    山西弘城
    日本保健物理学会研究発表会講演要旨集  2004
  • TLシートによる熱中性子線の二次元測定
    佐久間洋一; 山西弘城; 橋本光康; 佐藤博夫; 植木紘太郎; 石川雄三; 国枝悦夫; 古林徹; 義本孝明
    UTNL-R(東京大学大学院工学系研究科附属原子力工学研究施設)  2004
  • TLDを検出素子とした多層型中性子線量測定器の設計
    山西弘城
    日本原子力学会秋の大会予稿集  2004
  • 多層型エネルギー群別中性子線量測定器の開発
    山村直史; 飯田孝夫; 山根義宏; 山西弘城; 佐久間洋一; 植木紘太郎; 佐藤博夫
    日本原子力学会秋の大会予稿集  2004
  • 熱蛍光(TL)シートによる中性子線の二次元測定
    佐久間洋一; 山西弘城; 橋本光康; 佐藤博夫; 植木紘太郎; 石川雄三; 国枝悦夫; 古林徹; 成山展照
    理工学における同位元素・放射線研究発表会要旨集  2003
  • 環境水中トリチウム測定手法の簡素化
    飯田孝夫; 小金沢孝之; 緒方良至; 佐久間洋一; 山西弘城; 垣内正久; 佐竹洋; 鳥養祐二; 辻成人
    日本原子力学会春の年会要旨集  2003
  • 多層型エネルギー群別中性子線量測定器の設計
    山西弘城; 植木紘太郎; 佐久間洋一; 佐藤博夫
    日本原子力学会春の年会要旨集  2003
  • 放射線監視データを用いた放射線発生状況の分析
    山西弘城; 三宅均; 松岡啓介
    日本保健物理学会研究発表会要旨集  2003
  • 環境水中トリチウム測定の簡素化 (2)
    小金沢孝之; 飯田孝夫; 緒方良至; 佐久間洋一; 山西弘城; 垣内正久; 佐竹洋; 鳥養祐二; 辻成人
    日本保健物理学会研究発表会要旨集  2003
  • 医用中性子照射線量分布のTL式解析手法の評価研究
    佐藤博夫; 橋本光康; 佐久間洋一; 山西弘城; 植木紘太郎; 古林徹; 桜井良憲; 義本孝明; 石川雄三
    応用物理学会学術講演会講演予稿集  2002
  • ICP-MSおよび定置式および野外観測用のGe半導体検出器による土壌中U,Th系列放射能分析結果の相互比較 III 土岐地区における空間線量変動要因解明への適用
    馬場貴浩; 藤川陽子; 義本孝明; 池田恵美; 斎藤真弘; 福井正美; 山西弘城; 宇田達彦
    日本原子力学会秋の大会予稿集  2002
  • 環境水中トリチウム測定の簡素化
    佐久間洋一; 山西弘城; 飯田孝夫; 小金沢孝之; 緒方良至
    日本保健物理学会研究発表会要旨集  2002
  • 放射線監視システムRMSAFEによるバースト状X線の検出
    山西弘城; 三宅均; 松岡啓介
    日本保健物理学会研究発表会要旨集  2002
  • 環境水中トリチウム濃度測定の時間効率化および正確化
    小金沢孝之; 飯田孝夫; 佐久間洋一; 山西弘城; 緒方良至; 辻成人; 垣内正久; 佐竹洋
    理工学における同位元素・放射線研究発表会要旨集  2002
  • 電解濃縮を用いた環境水中トリチウム濃度測定の時間効率化
    小金沢孝之; 飯田孝夫; 佐久間洋一; 山西弘城; 緒方良至; 辻成人; 垣内正久; 佐竹洋; 鳥養祐二
    日本放射化学会年会・放射化学討論会講演要旨集  2002
  • 環境水中トリチウム測定の簡素化
    佐久間洋一; 山西弘城; 飯田孝夫; 小金沢孝之; 緒方良至; 垣内正久
    日本地球化学会年会講演要旨集  2002
  • 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  2001/03
  • 環境水中トリチウム測定の正確・迅速・簡素化
    佐久間洋一; 山西弘城; 飯田孝夫; 森泉純; 緒方良至; 辻成人
    KEK Proceedings  2001
  • ICP-MSおよび定置式および野外観測用のGe半導体検出器による土壌中U,Th系列放射能分析結果の相互比較 II アルカリ融解法の適用
    馬場貴浩; 藤川陽子; 義本孝明; 池田恵美; 斎藤真弘; 福井正美; 山西弘城; 宇田達彦
    日本原子力学会秋の大会予稿集  2001
  • 液シンによるトリチウム測定のための電解操作の簡素化 2
    佐久間洋一; 山西弘城; 飯田孝夫; 森泉純; 緒方良至; 辻成人
    理工学における同位元素・放射線研究発表会要旨集  2001
  • 多地点データを利用した実験起因放射線弁別評価法の検討
    山西弘城; 三宅均
    日本原子力学会秋の大会予稿集  2001
  • LHD実験のための中性子モニタリング用検出器の適正化  [Not invited]
    国際放射線防護学会第10回国際会議プ ロシーデ ィング  2000
  • Development of environmental tritium nonitoring system at Toki site.
    篠塚一典; 山西弘城; 宇田達彦; 佐久間洋一; 小坂尚樹; 辻成人
    日本放射化学会年会・放射化学討論会講演要旨集  2000
  • 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  1999/08
  • 土岐地区における大気中ラドン濃度の多地点測定
    山西弘城; 棚橋秀伍; 佐久間洋一; 宇田達彦; 河野孝央; 篠塚一典; 三宅均; 大林治夫; 飯田孝夫
    日本保健物理学会研究発表会要旨集  1999
  • LHD管理区域における入退出管理装置の開発
    河野孝央; 井上徳之; 佐久間洋一; 宇田達彦; 山西弘城; 棚橋秀伍; 本島修
    日本保健物理学会研究発表会要旨集  1999
  • 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  1998/09
  • 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  1998/09
  • 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  1998/09
  • Effect of hummidity on radon exhalation rate from concrete  [Not invited]
    H. Yamanishi; H. Obayashi; N. Tsuji; H. Nakayoshi
    Proc. 7th Tohwa Univ. Intern. Symposium, - Radon and Thoron in the human environment -  1998  WORLD SCIENTIFIC PUBL CO PTE LTD
     
    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.
  • 塩化カルシウムによる空気中トリチウム水濃度の測定
    中司等; 辻成人; 佐久間洋一; 山西弘城; 宇田達彦; 大林治夫
    理工学における同位元素研究発表会要旨集  1998
  • Radiation Monitoring System in Toki-Site, NIFS.
    山西弘城; 三宅均; 小平純一; 棚橋秀伍; 平林洋美; 佐久間洋一; 宇田達彦; 河野孝央; 大林治夫
    日本保健物理学会研究発表会要旨集  1998
  • Environmental Radiation Monitoring at Toki-area.
    宇田達彦; 棚橋秀伍; 佐久間洋一; 河野孝央; 山西弘城; 三宅均; 大林治夫; 吉田育司
    日本保健物理学会研究発表会要旨集  1998
  • Methane Decomposition on Nonvolatile Getter Material Loaded in Tritium Cleanup System.
    河野孝央; 佐久間洋一; 宇田達彦; 山西弘城; 棚橋秀伍; 兜森俊樹; 渋谷守
    プラズマ・核融合学会年会予稿集  1998
  • 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  1997/09
  • Design Studies of Helical Reactor FFHR. (1). Overview of FFHR Design.
    相良明男; 本島修; 山西弘城; 宇田達彦; 御手洗修; 田中知; 松井秀樹; 香山晃; 野田哲二
    日本原子力学会春の年会要旨集  1997
  • Development of Radiation Monitoring System Applicable to LHD Operation.
    三宅均; 山西弘城; 宇田達彦; 佐久間洋一; 平林洋美; 小平純一; 棚橋秀伍; 大林治夫
    プラズマ・核融合学会講演会予稿集  1997
  • Comparative study of electromagnetic field measurement for facilities of Large Helical Device.
    宇田達彦; 山西弘城; 平林洋美; 棚橋秀伍; 大林治夫; 中司等; 薄井弘道; 辻成人
    日本保健物理学会研究発表会要旨集  1997
  • Design Studies of Helical Reactor FFHR. (3). Safety Analysis of FFHR System.
    宇田達彦; 相良明男; 本島修; 山西弘城; 田中知; 寺井隆幸
    日本原子力学会春の年会要旨集  1997
  • Environmental Radiation Monitoring at Toki-area.
    宇田達彦; 棚橋秀伍; 佐久間洋一; 河野孝央; 山西弘城; 三宅均; 大林治夫
    プラズマ・核融合学会年会予稿集  1997
  • Measurement system of tritium concentration in the air by calcium chloride.
    中司等; 辻成人; 薄井弘道; 佐久間洋一; 山西弘城; 宇田達彦; 大林治夫
    日本保健物理学会研究発表会要旨集  1997
  • Dry Tritium Cleanup System for a Large Fusion Experimental Device. (2).
    佐久間洋一; 棚橋秀伍; 宇田達彦; 山西弘城; 兜森俊樹; 加藤敬; 渋谷守
    日本保健物理学会研究発表会要旨集  1997
  • Study of leakage X-rays measurement by Imaging Plate.
    加藤明己; 三宅均; 山西弘城
    理工学における同位元素研究発表会要旨集  1997
  • Design Studies of Helical Reactor FFHR. (4). T Breeding and Shielding.
    山西弘城; 相良明男; 本島修; 田中知; 寺井隆幸
    日本原子力学会春の年会要旨集  1997
  • 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  1996/09
  • Measurement of air exchange rate and radon exhalation rate from building wall(共著)  [Not invited]
    H. Yamanishi
    Proc. 7th intern. Congress, Indoor Air '96  1996
  • Development of a dual type ionization chamber system for burst n-X mixed fields  [Not invited]
    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  1996  INT RADIATION PROTECTION ASSOC
  • バースト状X-n混合場測定用双子型電離箱の開発(共著)  [Not invited]
    国際放射線防護学会第9回国際会議プロシーディング  1996
  • Preliminary Design of Tritium Clean-up System for the LHD. (2).
    佐久間洋一; 宇田達彦; 山西弘城; 平林洋美; 兜森俊樹; 加藤敬; 横沢実; 守谷泰博
    プラズマ・核融合学会年会予稿集  1996
  • Examination on dry-type tritium removal equipment for air discharge of nuclear fusion test equipment.
    佐久間洋一; 宇田達彦; 山西弘城; 平林洋美; 兜森俊樹; 横沢実; 加藤敬; 守谷泰博
    日本保健物理学会研究発表会要旨集  1996
  • Variation of Radon Concentration in a Room with Low Ventilation Rates. (3).
    辻成人; 中司等; 中吉久雄; 阿知波一生; 山西弘城; 平林洋美; 大林治夫; 下道国; 飯田孝夫
    日本保健物理学会研究発表会要旨集  1996
  • The measurement of radiation in heated peripheral equipments of nuclear fusion test equipmen by TLD .
    加藤明己; 三宅均; 小平純一; 大林治夫; 佐久間洋一; 山西弘城; 金子修; 竹入康彦
    KEK Proceedings  1995
  • The development of burst corresponding radiation monitor system RMSAFE. (II).
    三宅均; 小平純一; 大林治夫; 山西弘城; 佐久間洋一
    KEK Proceedings  1995
  • Blanket design of helical type fusion reactor (FFHR). ( Part 2 ).
    相良明男; 本島修; 山西弘城; 渡辺清政; 御手洗修; 寺井隆幸; 松井秀樹; 香山晃; 野田哲二
    核融合エネルギー連合講演会予稿集  1995
  • Characteristics test of an ionization chamber for dosimetry in an X-n interminglement field.
    山西弘城; 小平純一; 大林治夫; 佐久間洋一; 三宅均; 宇田達彦; 山本幸佳; 辻本忠; 義本孝明
    核融合エネルギー連合講演会予稿集  1995
  • Preliminary Design of Tritium Clean-up System for the LHD.
    佐久間洋一; 宇田達彦; 山西弘城; 大林治夫; 三宅均; 加藤敬; 横沢実
    プラズマ・核融合学会年会予稿集  1995
  • Actual condition of tritium gas oxidation activity of an environment sample in the National Institute for Fusion Science site.
    一政祐輔; 一政満子; 矢部智子; 大林治夫; 佐久間洋一; 山西弘城
    核融合エネルギー連合講演会予稿集  1995
  • Effective Volume Correction in a Pair of Cylindrical Proportional Counters Used for Tritium Measurement.
    佐久間洋一; 大林治夫; 山西弘城; 小平純一; 佐藤博夫
    プラズマ・核融合学会年会予稿集  1994
  • Charachteristics of the Outdoor Radiation Monitoring System in NIFS.
    小平純一; 大林治夫; 佐久間洋一; 山西弘城
    プラズマ・核融合学会年会予稿集  1994
  • Conceptual Design of Helical Type Fusion Reactor(FFHR).
    相良明男; 本島修; 渡辺清政; 今川信作; 山西弘城; 御手洗修; 井上徳之; 大薮修義; 山本純也
    プラズマ・核融合学会年会予稿集  1994
  • Variation of radon and radon progeny in a room with low ventilation rate  [Not invited]
    Proc. 6th intern. Congress, Indoor Air '93  1993
  • 低換気率室内空間におけるラドンとその娘核種濃度の変動  [Not invited]
    室内の空気質及び気候に関する第6回国際会議プロシーディング  1993
  • Radiation Shielding Analysis of Large Helical Device Facility.
    山西弘城; 小川雄一; 佐久間洋一; 大林治夫; 本島修; 半田博之; 成田均; 林克巳; 山田光文
    日本原子力学会春の年会要旨集  1993
  • Emitted X-ray Profile in the Circumference of JIPP T-II U Tokamak.
    小平純一; 山西弘城; 佐久間洋一; 大林治夫; アダチ ケイゾー; 東井和夫
    プラズマ・核融合学会年会予稿集  1993
  • Synthesis of Tritium-Free Water for Liquid-Scintillation Counting.
    佐久間洋一; 小平純一; 山西弘城; 大林治夫
    日本原子力学会秋の大会予稿集  1993
  • Atmospheric Tritium Concentrations at Toki Area.
    岡井富雄; 百島則幸; 高島良正; 大林治夫; 佐久間洋一; 小平純一; 山西弘城
    日本原子力学会秋の大会予稿集  1992
  • Investigation of Time Variation in Environmental Dose and Its Component at Toki Site.
    AKHMAD; 下道国; 池辺幸正; 大林治夫; 佐久間洋一; 山西弘城; 小平純一
    日本原子力学会秋の大会予稿集  1991

Works

  • Sensitivity of radiation detector for cosmic ray
    1998 -2000
  • Variation of radon and its progeny concentration in a room.
    1992 -1996

MISC

Research Grants & Projects

  • Japan Society for the Promotion of Science：Grants-in-Aid for Scientific Research
    Date (from‐to) : 2014/04 -2016/03 
    Author : IHARA Tatsuhiko; TANAKA Naomichi; KITAOKA Satoshi; YAMANISHI Hirokuni
     
    The decontamination rate of about 60% has attained for the cesium contamination soil of the Yamakiya Kawamatamachi Elementary School schoolyard by electrophoresis method at which the soil was ground preliminary with the citrate using the planet ball mill. In the pilot scale experiment conducted in the local experiment, the decontamination rate of 70% was obtained against 5 kg of contaminated soil. About the porous aluminum electrode used for the electrophoresis apparatus, the cesium occlusion capability inside an electrode was investigated for the pseudo-contaminated water which used the stable isotope cesium chloride. As a result, electric occlusion of the cesium is promptly carried out with application of voltage, and even if the occluded cesium makes polarity of an electrode reverse, it is not released, and it can be expected as cesium contamination water treatment technology.
  • Japan Society for the Promotion of Science：Grants-in-Aid for Scientific Research
    Date (from‐to) : 2013/04 -2016/03 
    Author : IIMOTO Takeshi; YAMANISHI Hiroki; Fujimoto Noboru; KIKKAWA Toshiko; MIURA Ryuichi; HAYASHI Rumiko; KAKEFU Tomohisa; TAKAKI Rieko; OZAKI Satoru; MIKADO Shogo; TAKAHATA Yuji; MURAISHI Yukimasa
     
    The purpose of this study is to develop radiation education modules which are requested by school teachers who are the core of the human resource development as a foundation for safety culture improvement. In the viewpoint of the field of radiation measurement, we developed a simple radiation detector for school education, based on the mechanism of the natural atmospheric pressure air GM counter. In the viewpoint of the field of education and social psychology, we investigated the latest situation of (1) information spread activities on radiation science and technology in various facilities, (2) nuclear and radiation education for secondary school students and teachers in foreign countries, and (3) expert development in the nuclear and radiation fields. We developed a simple tool for radiation education and practice modules. We utilized the modules in domestic and foreign secondary schools experimentally.
  • 核融合実験施設における放射線安全
    共同研究
    Date (from‐to) : 1991/04 -2011/03
  • 放射化物のクリアランス検認方法に関する検討
    Date (from‐to) : 2008
  • 宇宙線に対する放射線測定器の感度差
    共同研究
    Date (from‐to) : 1998 -2000 
    Author : 山西 弘城
  • 低換気率室内空間のラドン濃度変動要因に関する検討
    共同研究
    Date (from‐to) : 1991 -1998
  • 遠隔の放射線源の飛来方向特定
    共同研究
    Date (from‐to) : 1997 
    高所や遠隔にあるガンマ線源や中性子線源の飛来方向を特定するとともに、線源特性の推定を可能にする測定システムを開発する。
  • コンクリート片からのラドン散逸率の湿度依存性
    Date (from‐to) : 1993 -1996 
    Author : 山西 弘城
  • 実験室内環境におけるラドンとその娘核種濃度の変動要因
    共同研究
    Date (from‐to) : 1992 -1996 
    Author : 山西 弘城
  • 日本学術振興会：科学研究費助成事業
    Date (from‐to) : 1995 -1995 
    Author : 山西 弘城
     
    本研究は、コンクリートからのラドン散逸率が湿度環境によって変化する様子を捉えるものである。 作成日と組成の同じコンクリート片(15cm径×5cm厚)3個について、まず、質量が一定値に落ち着くまで105℃で乾燥させた。その後、ラドン散逸面を限定するため、側面をプラスチックフィルムで巻いて隙間を接着剤で埋めた。ラドン散逸率測定は、検討の結果、コンクリート片を容器にいれて一定時間蓄積したラドンを電離箱に捕集し測定する方式とした。 3つのデシケータにそれぞれコンクリート片を入れ、除湿空気、加湿空気、これらの混合空気をそれぞれ約1リットル/分で流した。湿度をコントロールしやすいように曝露系全体を恒温器に入れ、30℃に制御した。各デシケータの温湿度はセンサによって連続測定している。湿度は、絶対湿度で3、10、25g/m^3の3種類に設定した。これらは乾燥状態(対照)、冬場、夏場の湿度に対応する。 曝露開始から1ヵ月後のコンクリート片の含水率はそれぞれ0.1、0.6、1.1%であった。含水率は乾燥重量との重量差を乾燥重量で除した値とした。一方でラドン散逸率はそれぞれ0.26、0.28、0.54Bq/(m^2・h)であった。曝露実験はまだ途中段階であるが、湿度環境の差異によるコンクリート片からのラドン散逸率の変化を観測できた。この傾向は、低換気率室内における空気中ラドン濃度の季節変化の測定結果とほぼ一致している。夏場は冬場の2倍程度の濃度になる。著者らは、この要因は壁からのラドン散逸率の季節変動であり、それにはコンクリート中の水分が関与していると予想している。本研究の現段階の測定結果はこれを支持している。今後、この曝露実験を継続し、長期間曝露の効果を確認していきたい。
  • Radiation Safety for Fusion Experiment
  • Variation of radon in a room with low ventilation rates

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