著者
古田 悦子
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.45, no.3, pp.253-261, 2010 (Released:2011-07-12)
参考文献数
15

Recently many Japanese wear jewelry as personal ornaments, particularly bracelets. The jewelry is made of gems, jewels, noble metals and so on. Some kinds of jewelry include much amount of radioactive elements more than that of natural range in ores which are in our living-environment. The radioactive concentrations of 25 kinds of jewels and gems, which were easily purchased on a market or through the Internet, were analyzed by HPGe. The bracelet which was made of ceramics showed the highest radioactive concentration and it was estimated as approx. 800 Bq g-1 of 232Th and 140 Bq g-1 of 238U by assuming radioactive equilibrium among the nuclides in the decay series. Moreover, there was a high radioactive concentration gem including 60 Bq g-1 of 232Th and 300 Bq g-1 of 238U. The radioactive materials added in the ceramics should be monazite analyzed by a prompt gamma-ray activation analysis method. Though the ceramics became the object of the NORM management by the concentration, the radioactivity of one bracelet does not exceed 8,000 Bq. So, all these jewelry samples do not have to manage as NORM as consumer products according to the guideline by Japanese government. However, the jewelry's activity by deliberate addition of radioactive materials is deemed to be unjustified exposure, that the ICRP led the consideration. It is considered that the NORM guideline should take in the consideration of ICRP and prohibit the addition of radioactive materials to jewelry.
著者
神谷 研二
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.49, no.4, pp.167-168, 2014 (Released:2015-12-18)
被引用文献数
1
著者
明石 真言
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.54, no.3, pp.149-150, 2019-10-29 (Released:2019-11-21)
著者
丸山 隆司
出版者
Japan Health Physics Society
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.21, no.4, pp.273-283, 1986 (Released:2010-02-25)
参考文献数
18
著者
山田 純也 橋本 周 瀬谷 夏美 羽場 梨沙 武藤 保信 清水 武彦 高崎 浩司 横山 須美 下 道國
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.52, no.1, pp.5-12, 2017 (Released:2017-04-22)
参考文献数
9
被引用文献数
2

The purpose of this study is to improve a quick method for estimation of 131I concentrations in the air using data measured by monitoring posts in case that a nuclear disaster occurs. In this method, 131I concentrations were estimated by multiplying 131I count rates of cloud-shine measured with Na(Tl) detector by concentration conversion factor. A previous study suggested that it was difficult to determine passing-through time of plume from temporal change of 131I count rates or dose rate. Our study applies the method for estimating passing-through time of plume from temporal change of noble gas counts. The 131I concentrations in the air at Oarai center, Japan Atomic Energy Agency resulting from the accident at the Fukushima Daiichi Nuclear Power Station were estimated by proposal technique. The result of comparison of this method with sampling method for 131I concentrations in the air were within factor 3.
著者
鈴木 隆司 岡野 安宏 杉浦 城春 猪越 幸雄
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.33, no.2, pp.163-170, 1998 (Released:2010-02-25)
参考文献数
16
被引用文献数
1 2

The concentrations of medically used radionuclides in activated sludge samples were measured for 10 waste water treatment plants (WWTP) in Tokyo from October 1983 to March 1994. The nuclides 99mTc, 67Ga, 111In 123I 131I and 201Tl, among others, could be detected, but these concentration levels were lower than the legal concentration limits in Japan. The excess activated sludge is usually incinerated at WWTP; then the resulting ash is transported for reclamation in Tokyo Bay. Internal and/or external exposure doses were evaluated for the following cases: (1) The dose of the public attributed to radioactive iodine and 201Tl, which were released from the incinerator by burning sludge; (2) The dose of the workers during the process of transport and reclamation of the ash. As a result, the effective doses were sufficiently lower than the dose limit 1mSv/y. The decay of the radionuclides were calculated over a period of curing of the landfill. It was found that the radionuclides had decayed out to approximately one nuclide. The effective dose of the public can therefore be ignored. Moreover, it was clarified that the effective dose of the public resulting from 99Tc is negligibly low in value at the present time.
著者
雨宮 好文
出版者
Japan Health Physics Society
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.32, no.2, pp.135-138, 1997 (Released:2010-02-25)
参考文献数
2

3 0 0 0 OA 学会への期待

著者
上蓑 義朋
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.54, no.4, pp.203-204, 2019-12-27 (Released:2020-01-31)
被引用文献数
1
著者
Augustin JANSSENS
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.49, no.1, pp.5-6, 2014 (Released:2015-02-26)
参考文献数
8
著者
浜田 信行
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.52, no.2, pp.77-87, 2017 (Released:2017-07-29)
参考文献数
37
被引用文献数
4

In April 2011, the International Commission on Radiological Protection recommended reducing the occupational equivalent dose limit for the lens of the eye. Since then, discussions toward implementation of such a revised dose limit into national law have been made in various countries. In the United States of America (US), the National Council on Radiation Protection and Measurements (NCRP) established Scientific Committee 1-23 (SC 1-23) in January 2014 to provide guidance on whether existing dose limits for the ocular lens should be changed in the US, to which the author of this paper served as Consultant. In January 2017, NCRP published Commentary No. 26 “Guidance on radiation dose limits for the lens of the eye” which was prepared by SC 1-23. With this Commentary, NCRP now recommends reducing the occupational dose limit for the lens from equivalent dose of 150 mSv/year to absorbed dose of 50 mGy/year along with the use of relative biological effectiveness value for high linear energy transfer radiation. This review provides an outline of this Commentary.
著者
野口 宏 加藤 正平
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.20, no.1, pp.49-59, 1985 (Released:2010-02-25)
参考文献数
54

The literature on conversion of tritium gas to tritiated water in various environments is reviewed. The conversion mechanisms and the conversion rates are as follows.1. In the oxidation with oxygen and the isotopic exchange with water, tritium β-rays and metal catalyst are effective. The oxidation rate is -0.02%/day at initial tritium concentration ≤10-2Ci/l and -2%/day at 1Ci/l. In the presence of oxygen and water, it is not clear whether the exchange reaction occurs or not because of the small amount of data.2. For biological conversion, soil microorganisms contribute significantly. The conversion rate is greater than 10%/hr. The tritium gas deposition velocity, which includes the uptake rate of tritium gas by soil and the conversion. rate, ranges from 0.0025 to 0.11cm/sec and is influenced by temperature and moisture of the soil.3. Tritium gas is converted to the tritiated water througn the reaction with hydroxyl radical produced by sunlight in the atmosphere.
著者
中谷内 一也
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.34, no.4, pp.391-396, 1999 (Released:2010-02-25)
参考文献数
17

This paper discusses the threshold of carcinogen risk from the viewpoint of social psychology. First, the results of a survey suggesting that renunciation of the Linear No-Threshold (LNT) hypothesis would have no influence on the public acceptance (PA) of nuclear power plants are reported. Second, the relationship between the adoption of the LNT hypothesis and the standardization of management for various risks are discussed.
著者
Mochamad Adhiraga PRATAMA Shogo TAKAHARA Shinji HATO
出版者
日本保健物理学会
雑誌
保健物理 (ISSN:03676110)
巻号頁・発行日
vol.52, no.3, pp.200-209, 2017 (Released:2017-11-15)
参考文献数
37
被引用文献数
2

The purpose of this study is to identify the significance of the change in the intestinal absorption rate values the (ƒ1 value) to the change of ingestion dose coefficient following an acute intake of 134Cs and 137Cs. This study also attempted to provide a simple calculation method of ingestion dose coefficients given a specific value of ƒ1 and age groups by using linear regression models. In the range of 0-1, 10 different values of ƒ1 for 1-year, 5-year-old, and the adult group were chosen and used in a separate calculation by using, a biokinetic compartment model, DCAL. It was found that the lower values of ƒ1 lead to a significant decrease of the committed effective dose coefficient for an adult. Oppositely for children, the decrease of the coefficient was not as significant. This study also suggests that the significance of dose coefficient change due to the variation of ƒ1 substantially depends on the biological half-life of the radionuclide, the fraction of absorbed energy and the mass of organs and tissues in human body.