保健物理
Online ISSN : 1884-7560
Print ISSN : 0367-6110
ISSN-L : 0367-6110
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44 巻, 4 号
選択された号の論文の17件中1～17を表示しています
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  • 放射線のリスクコミュニケーションに係る基本的事項
    篠原 邦彦, 大内 浩子, 近本 一彦, 谷口 和史, 永井 博行, 森本 恵理子, 米澤 理加, 渡辺 浩
    原稿種別: 解説
    2009 年 44 巻 4 号 p. 374-379
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.374
    ジャーナル フリー
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    In the field of atomic energy and radiation utilization, radiation risk is considered as one of the social uneasy factors. About the perception of risks, there is a gap between experts and general public (non-experts). It is said that the general public tends to be going to judge risk from intuitive fear and a visible concrete instance whereas the experts judge it scientifically. A company, an administration or experts should disclose relating information about the risks and communicate interactively with the stakeholders to find the way to solve the problem with thinking together. This process is called “risk communication”. The role of the expert is important on enforcement of risk communication. They should be required to explain the information on the risks with plain words to help stakeholders understand the risks properly. The Japan Health Physics Society (JHPS) is the largest academic society for radiation protection professionals in Japan, and one of its missions is supposed to convey accurate and trustworthy information about the radiation risk to the general public. The expert group on risk communication of ionizing radiation of the JHPS has worked for the purpose of summarizing the fundamental matters on radiation risk communication. “Lecture on risk communication for the members of the JHPS.” which has been up on the JHPS web-site, and the symposium of “For better understanding of radiation risk.” are a part of the activities. The expert group proposes that the JHPS should enlighten the members continuously for being interested in and practicing risk communication of radiation.
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原著論文
  • 放射性物質による皮膚汚染時の線量評価
    加藤 秀起, 古賀 佑彦, 向山 隆史, 戸松 弘孝, 鈴木 友輔, 鈴木 昇一
    原稿種別: 原著論文
    2009 年 44 巻 4 号 p. 380-386
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.380
    ジャーナル フリー
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    In one of the accidents that might happen in the nuclear power station, there is a contamination accident caused by radioactive corrosion products during a periodic inspection. It is necessary to presume the skin absorbed dose from the adhesion area and the contamination density to forecast the level of the skin hazard by the adhesion of the radioactive substance. However, the data to forecast the local skin dose when the radioactive substance adhered handily is not maintained. In this paper, the absorbed dose in the skin surface neighborhood contaminated by radioactive corrosion products was calculated, and the relation between the adhesion area and the contamination density and the local absorption dose was derived. And, the approximate equation that forecast the integrated dose was derived from these data. As for the absorbed dose rate in depth 70 μm from the skin surface that became the index of the skin hazard, the contribution rate by 59Fe was the highest within 30 days, and the contribution of 60Co rose most after the 30th after the radioactive substance had adhered when the contamination density the adhesion area was the same. The relation between the initial contamination density and days that required it was graphed to reaching to the threshold by the integrated dose when the threshold dose in which the necrosis of the skin was caused was assumed to be 20 Gy. The absorbed dose commitment can be presumed from measurements of the contamination density by using this graph or the approximate equation.
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  • Verification of Validity of Isotope-Specific Exemption Levels for Surface Contamination Using Monte Carlo Calculation
    Haruyuki OGINO, Takatoshi HATTORI
    原稿種別: Original Paper
    2009 年 44 巻 4 号 p. 400-407
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.400
    ジャーナル フリー
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    Current surface contamination density standards are conservatively determined not for each nuclide but by the type of emitter. In the previous studies, isotope-specific exemption levels for surface contamination for representative nuclides were originally derived by developing a deterministic dose assessment model that can be applied throughout radiation, transport and waste safety fields. In this study, the effects of uncertainty in assumed parameters on the derived exemption levels were examined by developing a probabilistic dose assessment model using the Monte Carlo calculation. The criteria for the judgment of validities of the derived exemption levels were decided applying the concept of the representative person given by the International Commission on Radiological Protection (ICRP), the set of minimum dose constraint for the optimization of the radiological protection of the public revealed in a recent study and the probabilistic dose assessment model developed by the Nuclear Safety Commission (NSC) of Japan. Moreover, the effects of correlation in parameters on the results of probabilistic dose assessment are probabilistically examined by developing the function of specifying the random seeds independently for each parameter in the Monte Carlo calculation. These results verify the validity of the deterministically derived isotopespecific exemption levels for surface contamination.
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ノート
資料
  • 初期および二次被ばく医療機関の線量評価・汚染評価機能に関する現状調査
    山田 裕司, 明石 真言, 石榑 信人, 遠藤 章, 真田 哲也, 白石 久二雄, 静間 清, 鈴木 敏和, 高田 千恵, 中山 一成, 星 ...
    原稿種別: 資料
    2009 年 44 巻 4 号 p. 393-399
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.393
    ジャーナル フリー
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    The questionnaire on evaluation function for contaminations and doses was sent to the primary and the secondary radiation emergency hospitals in Japan by the network council for physical dosimetry in National Institute of Radiological Sciences (NIRS) designated as the tertiary hospital. The recovery percentage from the 88 hospitals was 70%. It turned out that six primary hospitals in 37 hospitals did not have even the basic instruments on radiation measurement such as GM counter and personal dosimeter. 64% of the secondary hospitals have the whole body counter, but its operation frequency including exercise was considerably low. It is thought that the main cause originates in a chronic manpower shortage and the budget shortfall seen by all the primary and the secondary hospitals. And also peculiar difficulty of correspondence to the radiation emergency medical treatment and the few experience might promote the problem. Thus the anxiety of the site staff had been appeared to the result of the questionnaire survey in shape like the opinion and the demand, etc. It will be necessary to advance the enhancement of training and to make the manual for the contaminations and the doses evaluation in the hospitals.
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  • Radioactivity and Radiation Levels in and around the Proposed Nuclear Power Plant Site at Rooppur
    Abdus Sattar MOLLAH, Shymal Ranjan CHAKRABORTY
    原稿種別: Technical Data
    2009 年 44 巻 4 号 p. 408-413
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.408
    ジャーナル フリー
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    The radioactivity concentrations in soil and water samples collected from 25 locations have been determined by using a gamma-ray spectrometry. Gamma-spectrometry measurements were made using a hyperpure germanium detector surrounded with shielding material to reduce the background counting rate. The EmcaPlus MCA emulation software was used for gamma-ray spectrum analysis. Results show that the concentrations of 238U, 232Th and 40K in the soil samples varied from 11.1 to 34.5 Bq.kg-1 with a mean of 17.9±4.9 Bq.kg-1, from 19.5 to 42.6 Bq.kg-1 with a mean of 26.6±5.6 Bq.kg-1 and from 289.1 to 511.1 Bq.kg-1 with a mean of 379.6±49.9 Bq.kg-1, respectively. The concentrations of 238U, 232Th and 40K in the water samples varied from 110.7 to 214.3 mBq.L-1 with a mean of 175.5±25.9 mBq.L-1, from 129.5 to 302.7 mBq.L-1 with a mean of 247.8±40.5 mBq.L-1 and from 299.7 to 467.9 mBq.L-1 with a mean of 379.6±45.3 mBq.L-1, respectively. The external indoor and outdoor background gamma radiation levels have also been measured by using an ionization chamber survey meter. The external indoor gamma dose rate is found to vary from 0.14 μGy.h-1 to 0.22 μGy.h-1 with a mean dose rate of 0.18 μGy.h-1. The outdoor dose rate is found to vary from 0.12 μGy.h-1 to 0.23 μGy.h-1 with a mean value of 0.17 μGy h-1. The annual average effective dose is found to be 0.96 mSv.y-1 (96 mrem.y-1) taking into account the indoor and outdoor occupancy factors 0.8 and 0.2 respectively. This value is comparable with those of world values. This study gives a baseline of radioactivity and external indoor and outdoor radiation levels in the proposed nuclear power plant site area at Rooppur and will be helpful to correlate the radioactivity measured after operation of the reactor.
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  • Evaluation of Secondary Exposure Doses to Transportation and Medical Personnel in the Radiation Emergency Medicine
    Hideki KATO, Sukehiko KOGA, Takashi MUKOYAMA, Hirotaka TOMATSU, Yusuke ...
    原稿種別: Technical Data
    2009 年 44 巻 4 号 p. 414-418
    発行日: 2009年
    公開日: 2011/01/12
    DOIhttps://doi.org/10.5453/jhps.44.414
    ジャーナル フリー
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    Radionuclide contamination is one of the accidents that might occur while carrying out a periodical inspection of nuclear power stations during normal reactor operation. When such an accident occurs, rescue and medical personnel, involved in transporting and treating affected workers run the risk of exposure to secondary radiation. In this study, the ambient dose equivalent rate at a certain distance from the surface of the human body contaminated with typical radioactive corrosion products was calculated. Further, the relationships among the adhesion area, contamination density, and secondary exposure dose were clarified. The secondary exposure dose and permissible working hours in a radiation emergency medicine were estimated by presenting these relationships in the form of a chart and by specifying the contamination levels.
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