巻号一覧
25 巻 (1990)
- 4 号 p. 349-
- 3 号 p. 209-
- 2 号 p. 107-
- 1 号 p. 3-
25 巻, 4 号
選択された号の論文の10件中1～10を表示しています
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小野 双葉, 田中 知, 山脇 道夫1990 年 25 巻 4 号 p. 349-359
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーDesorption behavior of tritium from various materials (type 316 stainless steel, copper, and borosilicate glass) contacted with tritiated gas was studied.
It was found that the tritium once sorbed could not be easily desorbed in a stream of nitrogen gas (dry, wet, or containing 10% hydrogen). Heat treatment was found to be effective for desorption of tritium from metal samples but was very difficult for desorption of tritium from glass samples.抄録全体を表示PDF形式でダウンロード (1112K) -
木村 雄一郎, 小川 喜弘, 本田 嘉秀, 桂山 幸典1990 年 25 巻 4 号 p. 361-368
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーThe uptake and accumulation of 60Co, 106Ru, and 144Ce by a phytoplankton, chlorella, in seawater, as well as the particulate behavior of these radionuclides, were studied. The following results were obtained. (1) The uptake and accumulation of 60Co increased during the logarithmic growth phase and reached an equilibrium at stationary phase, while those of 106Ru and 144Ce reached the maximum level after one day, followed by reduction during the logarithmic growth phase and an equilibrium at stationary phase. (2) The adsorption of 60Co on dead cells showed a similar pattern to that in live cells, but no change was noted in 106Ru and 144Ce. (3) The examination of particulate formation of the radionuclides using HAWP Millipore filters demonstrated that most of 60Co was contained in the filtrate, while about 4% of 106Ru and 18% of 144Ce were captured on the filters. (4) The concentration factors were 2.6×102 for 60Co, 3×102 for 1106Ru, and 6.5×103 for 144Ce. (5) The different patterns for the uptake of 60Co and 106Ru or 144Ce were attributed to the changes of radioactivity concentration due to their particulate formation in the media.抄録全体を表示PDF形式でダウンロード (4217K) -
山本 久夫, 畠山 智, 法村 俊之, 土屋 武彦, 白石 文夫1990 年 25 巻 4 号 p. 369-371
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーThe concentration of the uranium contained within the front glass of CRT (cathode ray tube) of television sets was estimated with fission-track detectors. It was found that atoms of the uranium were distributed almost uniformly within the glass, and that the concentration was 0.6-18ppm for the glass of CRT, whereas it was 0.3-0.7ppm for the other glass such as a laboratory dish. Namely, the value of the highest concentration of the former was several-tens times as large as that of the latter.抄録全体を表示PDF形式でダウンロード (1925K) -
阿部 史朗1990 年 25 巻 4 号 p. 373-384
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーAt the 1987 Workshop of the Speciality Committee for Radon and Thoron Measurements, an intercomparison among twelve organization in Japan that practice measurements of radon and radon daughter products was carried out as one of the Visiting Researchers Programs of the Kyoto University Research Reactor Institute. Measured items were radon concentration (222Rn), daughter concentartion assuming radioactive equilibrium among radon daughter products in air (Rn-dts), total 218Po, 214Pb, and 214Bi concentrations, the potential alpha energy (PAE) concentration, and unattached 218Po, 214Pb, and 214Bi concentrations; not all of these items were measured by every participant. Each participant selected an instrument or a method in compliance with his thought. The instruments and methods used were as follows: 222Rn: liquid scintillation method, a scintillation cell, an ionization chamber, a flow-type ionization chamber, a plane multiwire-electrode ionization chamber, electrostatic collecting method and charcoal trap method; radon daughter products: filter sampling method (two-count and/or three-count method); unattached radon daughter products: wire-screen method. Measurements were performed at two radon concentration levels of about 100Bq·m-3 and 400Bq·m-3, which were prepared by radon gas that emanated naturally from building walls to a laboratory room. The results were as follows: the coefficients of variance of averaged value were 7.7-16.2 for 222Rn, 13.9-20.7 for Rn-dts, 10.7-33.5, 11.6-15.3, and 11.9-13.1 for total 218Po, 214Pb, and 214Bi, respectively, 41.8-43.1 for PAE, and 33.1, 16.7, and 30.8 for unattached 218Po, 214Pb, and 214Bi, respectively. Considering the differences between the various applied techniques for measuring radon, fair agreement between the obtained concentration data was observed, whereas discrepancies of a factor of two or three were observed among the obtained PAE concentration data.抄録全体を表示PDF形式でダウンロード (1174K) -
松田 秀晴, 深谷 光春, 湊 進1990 年 25 巻 4 号 p. 385-390
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーNatural gamma-ray and cosmic-ray exposure rates were measured indoors and outdoors for 94 model houses of four housing centers in Nagoya to obtain basic data for estimation of the population dose. Influence of the structure of houses on indoor exposure rates and relationship between indoor and outdoor natural gamma-ray exposure rates were studied. Exposure rates were measured with a 1.5″φ×4″ NaI (Tl) scintillation counter and a 6″φ spherical plastic scintillation counter.
The mean indoor natural gamma-ray exposure rate in ferro-concrete buildings was about 40% higher than that in fireproof wooden houses, about 60% higher than that in light-weight steel-framed buildings, in fireproof wooden houses, it was also about 10% higher than in light-weight steel-framed building.
The ratio of indoor to outdoor natural gamma-ray exposure rate was found to be about 0.95±0.15, 0.77±0.10, and 0.72±0.13 for ferro-concrete buildings, fireproof wooden houses and light-weight steel-framed buildings, respectively.
The mean indoor cosmic-ray exposure rate in ferro-concrete buildings was 2.8μR/h, about 18% lower than the outdoors. The indoor cosmic-ray exposure rate in fireproof wooden houses and light-weight steel-framed buildings were 3.2μR/h, about 6% lower than the outdoors.抄録全体を表示PDF形式でダウンロード (677K) -
長岡 鋭, 森内 茂1990 年 25 巻 4 号 p. 391-398
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーAMS/NEST (Aerial Measurement System/Nuclear Emergency Search Team) executed emergency radiation monitoring using aircrafts at the time of the nuclear accident occurred at Three Mile Island-II reactor, U. S. A. in 1979. Motivated by this activity, Japan Atomic Energy Research Institute started a series of research and development of aerial survey system in 1980, and completed it in 1985. This system was named ARSAS (Aerial Radiological Survey and Assessment System).
ARSAS, loaded on board a helicopter, can measure wide range of gamma radiation field (10nGy/h-10mGy/h) and position of the helicopter. These data are recorded at every second without lack of acquisition. Using this system, one can get useful data for emergency countermeasures, such as isopleth map of dose rates, information about the direction of radioactive plume, release rate of radionuclides from the stack, and so on. This article mentions about the outline of ARSAS.抄録全体を表示PDF形式でダウンロード (1047K) -
滝本 察春1990 年 25 巻 4 号 p. 399-409
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーPDF形式でダウンロード (1102K) -
小佐古 敏荘1990 年 25 巻 4 号 p. 411-418
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーPDF形式でダウンロード (746K) -
放射性医薬品の製造側からみた医療施設における放射線防護について近藤 民夫1990 年 25 巻 4 号 p. 426-429
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーPDF形式でダウンロード (528K) -
保健物理に期待する岩井 敏1990 年 25 巻 4 号 p. 430
発行日: 1990年
公開日: 2010/02/25
ジャーナル フリーPDF形式でダウンロード (146K)
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