保健物理
Online ISSN : 1884-7560
Print ISSN : 0367-6110
ISSN-L : 0367-6110
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50 巻, 1 号
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原著論文
  • 放射性物質により汚染された災害廃棄物の道路への再利用に伴う被ばく線量評価
    澤口 拓磨, 武田 聖司, 木村 英雄, 田中 忠夫
    原稿種別: 原著論文
    2015 年 50 巻 1 号 p. 36-49
    発行日: 2015年
    公開日: 2015/12/18
    DOIhttps://doi.org/10.5453/jhps.50.36
    ジャーナル フリー
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    It is desirable that the disaster wastes contaminated by radioactive cesium after the severe accident at the Fukushima Nuclear Plant are reused as much as possible in order to minimize the quantity to be disposed of. Ministry of the Environment showed the policy that the wastes containing cesium of higher concentration than the clearance level (100 Bq/kg) were reusable as materials of construction such as subbase course materials of pavements under controlled condition with measures to lower exposure doses. In this study, in order to provide technical information for making a guideline on the use of contaminated concrete materials recycled from disaster wastes as pavement, doses for workers and the public were estimated, and the reusable concentration of radioactive cesium in the wastes was evaluated. It was shown that the external exposure of the public (children) residing near the completed pavement gave the minimum radiocesium concentration in order to comply with the dose criteria. The recycled concrete materials whose average concentration of cesium lower than 2,700 Bq/kg can be used as the subbase course materials of pavements.
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  • 放射性セシウムで汚染した木質チップの再利用に係わる線量評価
    高井 静霞, 関 優哉, 木村 英雄, 武田 聖司
    原稿種別: 原著論文
    2015 年 50 巻 1 号 p. 50-66
    発行日: 2015年
    公開日: 2015/12/18
    DOIhttps://doi.org/10.5453/jhps.50.50
    ジャーナル フリー
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    Wood and wooden wastes potentially contaminated by radioactive cesium released by Fukushima Daiichi Nuclear Power Plant have been reused for various purposes as wooden chips. The Ministry of the Environment indicated that the general disaster wastes including the wooden wastes were reusable with the criteria of total radioactive cesium (cesium-134 and cesium-137) concentration of 100 Bq/kg. The criteria were determined, based on the existing clearance level of concrete and metal generated at nuclear power plant and not on dose estimation for reuse of wooden chips. The purpose of this study is to confirm the validity of the criteria by the dose estimation approach. We investigated actual conditions og production and use for main five reuse purposes of wooden ships around Fukushima. On the basis of this investigation, exposure pathways and parameters for workers and public involved with the reuse of wooden chips were selected. We calculated dose for the exposure pathways and evaluated radioactive concentrations of wooden chips corresponding to dose criteria for safety reuse of radioactive materials. From the calculation result, all radioactive concentrations corresponding to the dose criteria are more than the reuse criteria of 100 Bq/kg, which ensures the validity of the criteria for the safety of present reuse of wood and wooden wastes.
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解説
  • 水晶体の放射線防護に関する専門研究会中間報告書 (IV)
    ―ICRP及びICRUの水晶体線量評価法―
    赤羽 恵一, 飯本 武志, 伊知地 猛, 岩井 敏, 大口 裕之, 大野 和子, 川浦 稚代, 立崎 英夫, 辻村 憲雄, 浜田 信行, 藤 ...
    原稿種別: 解説
    2015 年 50 巻 1 号 p. 67-75
    発行日: 2015年
    公開日: 2015/12/18
    DOIhttps://doi.org/10.5453/jhps.50.67
    ジャーナル フリー
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    The International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU) have been defined operational quantities and protection quantities. Dose limits have been also recommended by the ICRP using protection quantities. These quantities and some related values for main radiation such as photons, electrons, and neutrons, are summarized in this article with some historical considerations. The ICRP indicated conversion coefficients for the lens of the eye as absorbed dose per fluence as protection quantities. Equivalent dose is not used because a protection quantity that uses radiation weighting factors is not intended to be calculated for tissue reactions. So far, the ICRP has not indicated a specific RBE value for cataract formation. Operational quantities are used for measurements. There have been three types of phantoms, namely a slab phantom, a reduced phantom, and a cylindrical phantom, but none of them has been definitely recommended for the lens of the eye by the ICRP or the ICRU. Although conversion coefficients to personal dose equivalent, Hp(3), for electrons have been recommended, no other conversion coefficients to personal dose equivalent for the lens of the eye has been indicated by the ICRP or the ICRU. However, there have been several studies described personal dose equivalent. Ambient dose equivalent, H*(3), and directional dose equivalent, H'(3,a), have been indicated in several limited conditions by the ICRP and the ICRU. These status are overviewed in this article.
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  • 水晶体の放射線防護に関する専門研究会中間報告書 (V)
    ―わが国の各分野における従事者の水晶体被ばく及び防護の現状―
    赤羽 恵一, 飯本 武志, 伊知地 猛, 岩井 敏, 大口 裕之, 大野 和子, 川浦 稚代, 立崎 英夫, 辻村 憲雄, 浜田 信行, 藤 ...
    原稿種別: 解説
    2015 年 50 巻 1 号 p. 76-89
    発行日: 2015年
    公開日: 2015/12/18
    DOIhttps://doi.org/10.5453/jhps.50.76
    ジャーナル フリー
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    For many Japanese radiation workers in the medical, nuclear and other industrial fields, the equivalent dose of the lens of the eye will be sufficiently lower than the new ICRP dose limit. However, the dose of the lens of the eye for medical staff members who are engaged in interventional radiology and cardiology may exceed the new ICRP dose limit, especially when they are exposed closely to higher scatter radiation for a long time. In addition, the radiation dosimetry and radiation protection for emergency and recovery workers in the Fukushima Daiichi Nuclear Power Plant (FNPP1) are important issues. Thus gathering information related to the radiation dose and protection for Japanese radiation workers is important to a discussion regarding implementation of the new ICRP dose limit for the lens of the eye for Japanese regulations and planning radiation dose reduction measures. In this paper, recent studies and issues regarding radiation exposure and protection in the medical, nuclear and other industrial fields, as well as for emergency and recovery workers in the FNPP1 were summarized.
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レポート
  • Position Dependence for Count Rates in a Polyethylene Naphthalate Survey Meter
    Philip NGUYEN, Hidehito NAKAMURA, Yoshiyuki SHIRAKAWA, Tatsuya YAMADA, ...
    原稿種別: Report
    2015 年 50 巻 1 号 p. 90-93
    発行日: 2015年
    公開日: 2015/12/18
    DOIhttps://doi.org/10.5453/jhps.50.90
    ジャーナル フリー
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    A thin polyethylene naphthalate (PEN) sheet (72 × 140 × 0.5 mm) with one face enhanced with prism treatment was used for a survey meter. PEN has a relatively high effective refractive index of 1.70, which directly affects light propagation generated in the sheet. We show its radiation counting response at a 9 × 23 array of different locations on the detection window of the PEN survey meter, when irradiated with beta particles from a 90Sr radioactive source. The variability in radiation counts on the detection window, obtained by dividing the maximum value by the minimum value, was 1.23 along the Y-axis and 1.05 along the X-axis. This knowledge can be useful in the design of radiation detectors mounting PEN sheets.
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