RADIOISOTOPES
Online ISSN : 1884-4111
Print ISSN : 0033-8303
ISSN-L : 0033-8303
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Volume 36, Issue 6
Displaying 1-11 of 11 articles from this issue
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  • Development of a 137Cs Scattering Gamma-ray Source for Nuclear Gauge
    Shigemasa ENOMOTO, Yoshio HIGASHIYAMA, Hajime MIYAUCHI
    1987 Volume 36 Issue 6 Pages 253-260
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_253
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    An assembled radiation source device emitting a few hundred keV gamma-rays was developed for industrial radiation gauges by utilizing Compton scattering of 137Cs gamma-rays with an appropriate scatterer. The effects of design parameters of the source device on the energy distribution of emitted photons and their intensities were investigated by computer aided Monte Carlo simulation in advance of experimental examinations. The investigation on the shape and material of the scatterer resulted in the choice of a cylindrical backscatterer made of iron for the source device. The backscatterer designed has an outer size of 140×70 mm, an inner hollow space of 100×50 mm, and a wall thickness of 20 mm. The source device fabricated consists of a tiny sealed 137Cs gamma-ray source, the cylindrical iron backscatterer, and a lead shield against primary gamma-rays. The characteristics of the gamma-rays emitted from it were experimentally examined. The energy spectrum ranges from about 100 to 300 keV. The output intensity at a distance of 300 mm is 0.65 mR h-1 mCi-1 (137Cs) and almost uniform within a circular plane of 40 mm radius vertical to the central axis of the source device. The gamma-ray absorption characteristics by iron plates shows that the source device has place just between 241Am and 137Cs sources for radiation gauging use.
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  • Utilization of 67Ga-Citrate for the Measurement of Histamine-Induced Edema in Anesthetized Rats
    Hiroyuki KOHNO, Kohji OCHIAI, Yasuhito OHKUBO, Akiko KUBODERA
    1987 Volume 36 Issue 6 Pages 261-264
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_261
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    Radioactivity of the histamine-induced paw edema was measured after intravenous injection of 67Ga-citrate in anesthetized rats. The radioactivity was fluctuated almost pararel with the edema rate following subcutaneous injection of histamine. Both the radioactivity and the edema rate were almost equally reduced by pretreatment with chlorpheniramine, an antihistaminic agent.There was a good correlation between the edema rate and the radioactivity. These results suggest that 67Ga-citrate is useful for the pharmacological study of antiinflammatory drugs, or is available for measuring the vascular permeability.
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  • Study for Quantitative Evaluation of Liver Volume and Accumulation Rate of Radioactive Agent with Single Photon Emission Computed Tomography
    Shizou SATO, Hisashi MIMURA, Takuo NODA, Kunzo ORITA, Yoshio HIRAKI, S ...
    1987 Volume 36 Issue 6 Pages 265-269
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_265
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    The quantitative evaluation on measurement of liver volume and the hepatic accumulation rate of the radioactive agent were studied with respect to body constitution, background activity and splenic consumption rate, using single photon emission computed tomography (SPECT) .
    The optical cut-off level for liver volume determination was proved to be reasonable as 35%. The background less than 5% had no influence to their clinical estimation with the error of less than 1.6%. The estimation of liver volume was mostly influenced by the splenic activity. When the splenic activity was increased two times of the hepatic activity, the liver volume was determined as 4.2% larger. Calculated counts by SPECT was well correlated with the hepatic activity.
    This study proved that SPECT was useful for the quantitative evaluation of the liver volume and the hepatic accumulation rate.
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  • Data Processing System of Personnel Exposure with Personal Computer
    Yoshimune OGATA, Kazuhito TAKESHIMA, Kunihide NISHIZAWA, Sadao KOJIMA, ...
    1987 Volume 36 Issue 6 Pages 270-277
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_270
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    This paper describes a software package that manages personnel exposure data with a personal computer. The exposure data is automatically transferred to the computer through a floppy disk supplied by film badge service companies. The computer processes data of about 4000 persons who belong to the 11 facilities and prints out the reports on the distribution of personal exposure level. This system made it possible for the radiation protection division to rapidly investigate the actual situation of occupational exposure with less laborious works.
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  • The Reactor Accident at Chernobyl': Identification of Radionuclides in Fallout in Niigata City
    Nobuko KAYAMORI, Naoyuki MURAKAMI, Tetsuya KONISHI
    1987 Volume 36 Issue 6 Pages 278-281
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_278
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    The fallout caused by the accident of Chernobyl' nuclear reactor has been monitored in Niigata City (April 30-June 3, 1986) . Twelve nuclides (131I, 132I, 129Te, 129mTe, 132Te, 134Cs, 136Cs, 137Cs, 103Ru, 99mTc, 140La, 140Ba) were identified in aerosol samples. The same nuclides plus 7Be were identified in rain-water. Gaseous and particle-bound 131I were separately trapped on a glass filter and a charcoal filter, respectively. Results indicate 50-60% of atmospheric 131I is gaseous and the rest is particlebound. Chloroform extraction of rain-water revealed that 40-60% of 131I in the rain-water sample exists in the form of IO3- and 131IO3- (131IO4-) /131I- seemed to increase with the lapse of time after the accident.
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  • Influence of Nuclear Reactor Accident at Chernobyl' on the Environmental Radioactivity in Toyama
    Miyuki MORITA, Miki SHOJI, Takashi HONDA, Masanobu SAKANOUE
    1987 Volume 36 Issue 6 Pages 282-285
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_282
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    The environmental radioactivity caused by the reactor accident at Chernobyl'was investigated from May 7 to May 31 of 1986 in Toyama. Measurement of radioactivities in airborne particles, rain water, drinking water, milk, and mugwort are carried out by gamma-ray spectrometry (pure Ge detector; ORTEC GMX-23195) . Ten different nuclides (103Ru, 106R, 131I, 132Te-I, 134Cs, 136Cs, 137Cs, 140Ba-La) are identified from samples of airborne particles. In the air samples, a maximum radioactivity concentration of each nuclide is observed on 13th May 1986. The time of the reactor shut-down and the flux of thermal neutron at the reactor were calculated from 131I/132I and 137Cs/134Cs ratio.
    The exposure dose in Toyama by this accident is given as follows: internal exposure; [thyroid] adult-59 μSv, child-140 μSv, baby-130 μSv, [total body] adult-0.2 μSv, child, baby-0.4μSv, external exposure; 7 μSv, effective dose equivalent; adult-9μSv, child-12 μSv, baby-11 μSv.
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  • A New Evaporation Procedure for Monitoring of Iodine-125 in Liquid Waste
    Minoru KAWAE, Mayumi WADA, Kiyomi MORI, Yoshimi SASAKI, Eiichi KANO
    1987 Volume 36 Issue 6 Pages 286-289
    Published: June 15, 1987
    Released on J-STAGE: September 07, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_286
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    A simplified monitoring method of 125I in liquid waste was devised. The waste water of 200 cm3 was taken on a Saran (polyvinylidene chloride) film covering a stainless steel vat.A stable iodine (20 mg) and sodium hydroxide (1 mmol) was added. The water was evaporated using an infra-red lamp. After heating to dryness, the Saran film was folded and transferred into a polyethylene tube. The radioactivity of 125I was counted with a well type NaI (Tl) scintillation counter. When a multi-channel analyzer was available for counting, an absolute decay rate of 125I was calculated with single and sum photo-peak counts. The radioactivity of 125I counted by a single-channel counter must be corrected with the counting efficiency of about 55 %, with a special emphasis of a self absorption of photons.
    The recovery of 125I for concentrations below the permissible level was more than 98%.
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  • Trends of Irradiated Foods in Japan and the World
    Hitoshi ITO
    1987 Volume 36 Issue 6 Pages 290-299
    Published: June 15, 1987
    Released on J-STAGE: July 21, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_290
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  • ICRP Publication 48, The Metabolism of Plutonium and Related Elements
    Osamu MATSUOKA
    1987 Volume 36 Issue 6 Pages 300-306
    Published: June 15, 1987
    Released on J-STAGE: July 21, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_300
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  • Handling Manual for Brachytherapy Sources. IV. Manual of Safety Use in Brachytherapy
    Akimune HAYAMI, Takashi MARUYAMA
    1987 Volume 36 Issue 6 Pages 307-316
    Published: June 15, 1987
    Released on J-STAGE: July 21, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_307
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  • [title in Japanese]
    1987 Volume 36 Issue 6 Pages A41P-A64M
    Published: June 15, 1987
    Released on J-STAGE: July 21, 2010
    DOIhttps://doi.org/10.3769/radioisotopes.36.6_A41P
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