著者
三浦 美和 林田 りか 高尾 秀明 小野 孝二 松田 尚樹
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.12, no.1, pp.46-53, 2013 (Released:2013-07-26)
参考文献数
21

From October to December 2010, just before the radiological accident at the Tokyo Electric Power Company Fukushima Daiichi nuclear power plant, 71 radiation professionals belonging to the radiation facilities in Japan were asked what they consider as a “safe” dose of radiation for themselves, their spouse, parents, children, brothers and friends. Although the “safe” dose varied widely from less than 1 mSv/y to higher than 100 mSv/y, the average dose was 35.6 mSv/y that was around the middle point between the exposure dose limits for annual average (20 mSv/y) and for any single year (50 mSv/y). Similar results were obtained from another surveys for the members of Japan Radioisotope Association (36.9 mSv/y) and for the Oita Prefectural Hospital (36.8 mSv/y). Among the family members and friends, the minimum average “safe” dose was 8.5 mSv/y for children, to whom 50% of responders claimed the “safe” dose less than 1 mSv. Gender, age and specialty of the responder also affected the “safe” dose. These findings suggest that the perception of radiation risk varies widely and that the legal exposure dose limit derived from the regulatory science may act as an anchor of safety even in radiation professionals. The different level of risk perception for different target groups in radiation professionals appears similar to those in non-professional whole population. The gap between these characteristics of real radiation professionals and the generally accepted picture of radiation professionals might take a part in a state of confusion after the radiological accident.
著者
吉田 茂生
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.1, no.1, pp.56-60, 2002 (Released:2011-03-17)
参考文献数
6

On the basis of many human tritium metabolic data accumulated in the Intense 14MeV Neutron Source Facility OKTAVIAN of Osaka University, Japan, until now, the characteristics of the measured data have been analyzed for bioassay samples of urine, exhaled water and water distilled from urine. It has been found that the tritium concentration of exhaled water is equal to that in water distilled from urine. A new method has been developed to follow up each metabolism of two chemical forms, that is, free water tritium (FWT) and organically bound tritium (OBT) in urine. In case of repeated tritium intake, it was found that the tritium concentration could be approximated by single exponential function corresponding to the fastest excretion component for about 50 days after each intake. In this approximate method, the biological half-life of second intake exceeded compared with that of first intake. The distribution ratio of FWT and OBT components changed at the next intake compared with the previous intake. Consequently, the ratio of the OBT component increased and brought the apparent increase of the biological half-life.
著者
松田 尚樹 吉田 正博 高尾 秀明 奥村 寛
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.5, no.1, pp.25-31, 2006 (Released:2011-03-17)
参考文献数
15

Recent amendments to the Law concerning Prevention of Radiation Hazards due to Radioisotopes, etc. and related regulations might afford the use of unsealed radioisotopes below the exemption limits outside controlled areas. This drastic change brought a great convenience to radiation workers, however, the practical management should take safety of both non-radiation workers and environments into consideration. Analysis of research activities using unsealed radioisotopes and a survey for radiation workers in Nagasaki University revealed that a number of biochemical experiments could be performed using radioisotopes below the exemption limits and that a half of respondents desired to use them in their own laboratories. Radiation safety management of those areas was also favored by most of responders, which would increase tasks of radiation safety staffs. Therefore, the rational and affordable safety management practice is required. On the basis of these results together with radiation safety managements in the U. S., Canada and the U. K., practical considerations for the use of radioisotopes outside controlled areas in Japan are discussed.
著者
大友 一輝 遠藤 美芽 村林 優樹 安部 圭亮 小野寺 真奈 鈴木 友裕 高橋 拓己 一ツ木 康晶 稲葉 洋平 千田 浩一
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.19, no.1, pp.2-10, 2020 (Released:2020-06-17)
参考文献数
18
被引用文献数
1

Recently, portable radiography has been performed in many facilities. In portable radiography, the distance between the radiological technologist and the patient is often close. Thus, exposure assessment and radiation protection for radiological technologist is important. However, the use status of personal protective equipment and the recognition of exposure differ depending on the facility and the individual. In addition, no detailed survey on the current state of portable radiography has been reported. Therefore, we conducted a questionnaire survey for radiological technologist involved in portable radiography. As the result of the questionnaire survey, it became clear that the protection status of radiological technologists during portable radiography varies depending on the facility, gender, and age. There were some opinions that it was difficult to keep away from the patient during portable radiography. In that case, it is desirable to wear protective equipment such as a protector.
著者
清水 喜久雄 中嶋 隆登 松尾 陽一郎 日高 雄二 佐藤 典仁 山本 幸佳
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.15, no.1, pp.52-58, 2016 (Released:2016-07-26)
参考文献数
16

The biological dosemeter that directly reflects cellular responses to ionizing radiations in living organisms would be useful for the protection of human health against exposures. We are aiming at developing a novel dosimetric system using DNA molecules as a radiation sensor. DNA molecules are irradiated and the resulting DNA damages are quantified by real-time PCR (quantitative PCR, qPCR) reactions.  We investigated DNA lesions caused by gamma ray or carbon ion particle irradiation and revealed that the extent of DNA amplification negatively correlated with the greatness of LET of exposed radiations. While ionizing radiations elicit not only DNA strand breaks but 8-hydroxy-2′-deoxyguanosine (8-OHdG) production, the amount of 8-OHdG produced by the high-LET carbon ion particle irradiation was at a similar level to that by low-LET gamma ray irradiation, demonstrating that 8-OHdG production was not affected by the greatness of LET. These results suggest that the extent of DNA strand breaks, not the amount of base damages such as 8-OHdG, is influenced by the greatness of LET and causes negative effect on DNA amplification.
著者
秋吉 優史
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.16, no.2, pp.72-78, 2017 (Released:2017-11-09)
参考文献数
11
被引用文献数
1

The technical feature of hardware and utilizing method of the high performance cloud chamber using a Peltier device are reported. Using this device, observation of not only alpha-rays tracks, but also beta-rays tracks, and furthermore, photoelectron tracks arisen from gamma rays or X-rays can be performed. Accordingly, this device provides intuitively radiological education of the difference in interaction with materials from a kind of radiation-rays.
著者
栗田 義幸 三枝 純 前田 智史
出版者
日本放射線安全管理学会
雑誌
日本放射線安全管理学会誌 (ISSN:13471503)
巻号頁・発行日
vol.15, no.2, pp.180-185, 2016 (Released:2016-11-22)
参考文献数
8

In 2012, JAEA has established a laboratory in Fukushima-city to implement radioactivity analysis of environmental samples. Key nuclides measured in this laboratory are 134Cs and 137Cs (radiocesium). For the purpose, situation of radiocesium inflow into the laboratory building and its effects on the analyses were investigated based on the gamma-spectrometry with germanium detectors. As a result, the surface densities of radiocesium in the laboratory was found to be far below the minimum detectable activities of survey instruments routinely used for the radiation control purposes.