Japanese Journal of Health Physics
Online ISSN : 1884-7560
Print ISSN : 0367-6110
ISSN-L : 0367-6110
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Volume 22, Issue 3
Displaying 1-15 of 15 articles from this issue
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  • Measurements of Dose Distribution of Neutrons and γ-rays in the Beam Transportation Room of a Cyclotron Building with Personnel Monitors
    Akira YAMADERA, Minoru FUJITA, Yuuiti IZUMI
    1987 Volume 22 Issue 3 Pages 251-258
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.251
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    The distribution of dose equivalents of neutrons and γ-rays emitted by the collisions of 35-MeV protons or 25-MeV deuterons with the copper of an analyser magnet, a chopper or a slit in the beam transportation room of the cyclotron building of Tohoku University were obtained by measurement with personnel monitors such as film badges, TLDs and CR-39 plastic track detectors. The CR-39 detectors were able to determine fast neutron doses without receiving disturbance of γ-rays. As for γ-rays, the readings with the film-badges were higher than those with the TLDs as much as about 20 to 30 percent. This might be due to the over response of the film badges for higher energy γ-rays (more than 1.25MeV). The doses of neutrons and γ-rays were greatly reduced by the stairs leading to the underground floor. The thermal neutrons showed almost the same values in the room except for the stairs.
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  • Experimental Study on Location for Workers in Nuclear Facilities to Wear Personal Dosimeter
    Tomoko KUSAMA, Tohru FUKUI, Katsumasa OTA, Morihisa KATO, Kenji NAKANO
    1987 Volume 22 Issue 3 Pages 259-264
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.259
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    In order to facilitate estimation of the dose-equivalent index or the effective dose equivalent for the purpose of radiation protection, we investigated how and where personal dosimeters should be worn by workers in nuclear facilities. Information on the dominant direction of incident radiation impinging on the body was of importance for this study, and we measured it on workers in two nuclear facilities. Sixty workers who were carried out periodic inspections of nuclear power plants were chosen as subjects. In one nuclear plant, each worker wore 2 film badges on the anterior and posterior surfaces of the trunk at chest level for one month, and in another, each worker wore four thermoluminescence dosimeters on the front, back and both sides of the trunk at waist level for 5 days, In 85per cent of all subjects, the doses on the anterior surface of the trunk were higher than those elsewhere. The average ratio between the posterior and anterior doses was 0.85. Thus, the majority of the incident radiation detected on workers in nuclear power plants fell on the anterior surface of the trunk. The results of this study suggested that one personal dosimeter worn on the front of the trunk is sufficient for routine individual monitoring purposes.
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  • Transfer of Gaseous Iodine from Atmosphere to Rough Rice, Brown Rice and Polished Rice
    Misako SUMIYA, Shigeo UCHIDA, Yasuyuki MURAMATSU, Yoichiro OHMOMO, Shu ...
    1987 Volume 22 Issue 3 Pages 265-268
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.265
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    Experiments were carried out in order to obtain information required for establishing transfer coefficients of gaseous iodine (I2) to rough rice, brown rice and polished rice. The gaseous iodine deposited on young rice plants before the heading period was scarcely found in the rough rice harvested at the full ripe stage. The biological half life of iodine in hull, however, was much slower than that in leaves of 14 days. The translocation of iodine from leaves and stalks to rough rice was not clearly recognized. Therefore, it was deduced that iodine found in brown rice mainly should originate from that deposited on the hull. The distribution ratios of iodine between rough rice and brown rice, and between brown rice and polished rice were 100:4 and 100:30 on 100 grains basis, respectively. If average normalized deposition velocity (Vd(m)) or derived deposition velocity (Vs) are given, the transfer coefficients of gaseous iodine to rough rice (TFr), brown rice (TFb) and polished rice (TFp) could be calculated.
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  • Development of Finger Dosimeter and Estimation of Maximum Shallow Dose Equivalent for Beta-rays
    Takashi TABARA, Tomoko KUSAMA
    1987 Volume 22 Issue 3 Pages 269-276
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.269
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    The present study was conducted to develop a finger dosimeter for beta-rays and to investigate a practical method for estimating, ‘maximum shallow dose equivalent’, as secondary limit of protection standard. The developped dosimeter is consisted of two Li2B4O7(Cu) TL elements, Al-shield and polyethylene case. To examine the relationship between the maximum shallow dose equivalent and receptor air dose measured by this dosimeter, dose distribution at various depths within a surface layer of human body was calculated by the Monte Carlo method in the case of irradiation from 35S, 147Pm, 45Ca 133Xe 131I, 85Kr, 204Tl 198Au 133I 32P and 90Sr-90Y. We used a model, such as receptor and dosimeter exposed to beta-rays under conditions of parallel beam with angles of incidence, 15°, 30°, 45°, 60°, 75° and 90°. Moreover, we irradiated the dosimeter with the sources of 35S, 131I, 198Au, 32P and 90Sr-90Y to verify the results of the calculation and to estimate minimum detectable dose of this dosimeter. Main results were as follows; 1) The point of maximum shallow dose equivalent for beta-rays was located at the depth of 7mg/cm2. 2) The conversion factors for receptor air dose to maximum shallow dose equivalent for beta-rays depended on the energies and angles of incidence of beta-rays. But, using the energy indexes which were difined as ratios of measured values of two TL elements, the conversion factors were decided independently of the energies and angles of incidence of beta-rays. 3) Minimum detectable dose of this dosimeter was 0.02mGy for beta-rays.
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  • Determination of Amounts of Radionuclides Released from Aluminium for Nuclear Material during Neutron Irradiation
    Toshibumi NOMURA, Tomoaki MATSUI, Kozo WATANABE
    1987 Volume 22 Issue 3 Pages 277-281
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.277
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    Fission products such as 89Rb, 131I and radionuclides such as 82Br, 203Hg have been released from the stack of JRR-2 during the reactor operation. It was assumed that these nuclides were generated in experimental holes which were made of Al. In order to certify fission product released from the natural uranium contained in Al material under neutron irradiation in the reactor, Al plates were experimentally irradiated in the irradiation capsule by using the vertical experimental hole of JRR-2. By means of sweeping with carrier gas, the radionuclides generated in the capsule were trapped with filterpaper of cellulose glass fibre, charcoal cartridge, while gaseous samples were collected in sampling vessel. Fission product such as 89Rb, 135Xe and radionuclides such as 82Br, 203Hg were found in the carrier gas. It became clear that the release of fission product originated from natural uranium existing in Al component as impurities, and radionuclides such as 82Br, 203Hg were generated from surface contaminants of Al in the experimental holes.
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  • A New Method for Evaluating Weak Leakage Gamma-Ray Dose Using a 3″φ×3″ NaI(Tl) Scintillation Spectrometer (III)
    Expanding of Applicable Energy Range
    Hideharu MATSUDA, Shigeko FURUKAWA, Tokishi KAMINISHI, Susumu MINATO
    1987 Volume 22 Issue 3 Pages 283-286
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.283
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    Applying the leakage gamma-ray which energy exceeding primary gamma-ray of K-40, namely 1.46MeV, a method previously reported, this is, three component method is still not satisfactory. Therefore, a better approach for expanding applicable energy range was examined. The result of measurements showed that there was sufficiently a correlation between background exposure rate and concentration of Th. The present method by background exposure rate was estimated from only concentration of Th contained in environment was practically usable technique. Though the measured error will increase, applicable energy range of three component method could expanded to about 2.5MeV by this technique.
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  • Evaluation of Background in CR-39 Detector for α-Particle Detection
    Nobuhito ISHIGURE, Osamu MATSUOKA
    1987 Volume 22 Issue 3 Pages 287-293
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.287
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    Background count of CR-39 detector (allyl diglycol carbonate) was measured as a function of storage time to evaluate the background levels at delivery and during storage, and so as to find the way of storage to suppress the background increase. An image processing TV device was used for measuring them. The etch pit density at delivery was 3.9 to 8.4mm-2; on the other hand, it was 0.13 to 0.38mm-2 for the pits larger than 12μm, where the surface removed by the etching was 19μm. Under this background the radon of 60Bq/m3 could be detected at 50% relative standard deviation for one month exposure on the area above 10mm2 by optimizing a threshold for etch pit diameter to be counted. The increase rate of background was 5.5mm-2/month when left exposed to the atmosphere. On the other hand, the CR-39 sealed in polyethylene bag showed the increase rate less than one forth of that of the exposed detector.
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  • Determination of Counting Efficiency of NaI(Tl) Detector for Radioactivity Measurement of Large γ-Ray Plane Sources
    Makoto YOSHIDA, Masato ISHIZAWA, Kentaro MINAMI
    1987 Volume 22 Issue 3 Pages 295-299
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.295
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  • Monte Carlo Calculation of Gamma Radiation Field Due to Iodine-131 Released to the Environment
    Naoto FUJINAMI, Shinobu ESAKA, Susumu MINATO
    1987 Volume 22 Issue 3 Pages 301-306
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.301
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    Properties of the radiation field due to iodine-131 distributed in the atmosphere and on the air-ground interface are evaluated by means of a one-dimensional Monte Carlo transport code for the propagation of gamma radiation in two medium geometry. The calculated data are presented on the height distribution and on the energy and angular distribution of flux density and exposure rate from the iodine-131 source.
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  • Interpretation of ICRP Publication 47: Radiation Protection of Workers in Mines
    Mizumi KURABAYASHI, Shinji TSUURA
    1987 Volume 22 Issue 3 Pages 307-313
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.307
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  • The Effect of Transuranium Elements, as Compared with Uranium
    Masanobu SAKANOUE
    1987 Volume 22 Issue 3 Pages 315-325
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.315
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  • Non-Radiation Risks of Labor Accident and of Daily Life in Japan
    Atsuhiko TAKEDA
    1987 Volume 22 Issue 3 Pages 327-336
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.327
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  • Present Status of Research and Development on the Treatment and Disposal of High-Level Radioactive Waste
    Noriaki SASAKI
    1987 Volume 22 Issue 3 Pages 337-346
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.337
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  • Letters (Vol. 22, No. 1)
    Seiji FUKUDA, Shinich SUGA
    1987 Volume 22 Issue 3 Pages 381-383
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.381
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  • Statement from the 1987 Como Meeting of the International Commission on Radiological Protection
    1987 Volume 22 Issue 3 Pages 384-388
    Published: 1987
    Released on J-STAGE: February 25, 2010
    DOIhttps://doi.org/10.5453/jhps.22.384
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