Japanese Journal of Health Physics

Sea Dumping of Radioactive Waste by the Soviet and Russia

Minoru HONAMI

1994 Volume 29 Issue 2 Pages 124-128
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.124

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Measures of Japanese Government concerning Sea Dumping of Radioactive Waste by the Former Soviet Union and Russia

Especially about the Marine Environmental Survey

Yasuhiro YUKIMATSU

1994 Volume 29 Issue 2 Pages 129-131
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.129

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Transport Process of Artificial Radionuclides in the Marine Environment

Katsumi HIROSE

1994 Volume 29 Issue 2 Pages 132-133
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.132

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Bioconcentration of Radionuclides in the Sea

Yuzuru SUZUKI

1994 Volume 29 Issue 2 Pages 134-137
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.134

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Artificial Radioactivity in Fisheries Resources

Katsuhiko YOSHIDA

1994 Volume 29 Issue 2 Pages 138-141
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.138

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Changes in ⁵⁹Fe Uptake into Erythrocytes and Chemically Separated Heme Fractions of Spleen and Femoral Bone Marrow after Irradiation with X-rays at Different Doses in OK-432 Treated Mice

Hisamasa JOSHIMA, Yoshiro AOKI

1994 Volume 29 Issue 2 Pages 143-153
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.143

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The radiation dose range in which OK-432 would promote the recovery of radiation-impaired erythropoiesis was investigated. C57BL/6J male mice were injected with a single dose of 5 KE of OK-432 1h before or 1h after irradiation with X-rays. Erythropoietic activity was measured by ⁵⁹Fe incorporation into circulating erythrocytes and the chemically separated heme iron fraction of erythropoietic tissues.
When irradiated with 94.5cGy to 567cGy of X-rays the uptake of ⁵⁹Fe into circulating erythrocytes was promoted within 20 days after irradiation by the treatment with OK-432. Treatment with OK-432 1h before otherwise lethal irradiation with 662cGy significantly enhanced the ⁵⁹Fe uptake into erythrocytes. These results demonstrate that OK-432 stimulates erythropoietic recovery in sub-lethally and lethally irradiated mice.
At long time intervals following irradiation with 567cGy or 662cGy of X-rays, the ⁵⁹Fe uptake into erythrocytes in the OK-432-treated group was quite similar to the corresponding non-irradiated controls. Further studies to ascertain whether OK-432 can be used as a radioprotective agent are currently in progress.

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The Passive Radon-Thoron Discriminative Dosimeter for Practical Use

Masahiro DOI, Sadayoshi KOBAYASHI

1994 Volume 29 Issue 2 Pages 155-166
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.155

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A passive radon-thoron discriminative dosimeter for practical use has been developed. The body of the practical R-T dosimeter is made of two hemispheric diffusion chambers of carbonized plastic whose diameters are 110mm and 70mm, respectively. These diameters are determined to improve the detection efficiency of radon as well as thoron and also the discrimination ratio of radon to thoron. Inner surface of the detector housing is smooth and free from electrified charge to assure the uniform deposition of radon and thoron progeny, because the detector housing is molded out of carbonized plastic as an anti-static material. In addition, structure of an air inlet has improved to contact more tightly with a glass fiber filter to prevent dust from entering the detector housing. The air inlet of the detector housing is also covered with a half-cutted hemispherical windbreak to protect the glass fiber filter from weathering and to stabilize the influence of convectional air flow on the radon and thoron entry rate into two hemispherical diffusion chambers of the dosimeter. The results of calibration exercises showed that the lower detection limit of radon and thoron concentrations were estimated to be 5.1Bqm^-3 and 7.9Bqm^-3 respectively in 2 months exposure. And an interim measurement in the concrete cellar proved that the practical R-T dosimeter has enough specifications to be used in the large-scale radon-thoron discriminative survey.

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Experimental Study on the Removal of ¹⁴C in Radioactive Liquid Waste

Kenzo NISHIMAKI, Akio KOYAMA

1994 Volume 29 Issue 2 Pages 167-172
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.167

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Carbon-14 gives the largest collective dose commitment to the world population among the nuclides which are discharged from nuclear fuel cycle facilities, therefore this is a very important nuclide from the viewpoint of radiation protection. In neutron fields as in the vicinity of the cores of nuclear reactors, there are several nuclear reactions which regularly generate ¹⁴C in operation. Carbon-14 generated in water is contained in radioactive liquid waste on the occasion of maintenance of reactors etc. Because ¹⁴C emits only weak β-rays, it is difficult to detect ¹⁴C in liquid waste by ordinary monitoring methods. Therefore ¹⁴C has not been recognized as a major object for the treatment of radioactive liquid waste, and there has been little information on the treatment of ¹⁴C in water.
In this study, we performed experiments on the treatment of ¹⁴C in liquid waste by conventional treatment methods for radioactive liquid waste such as ion exchange, chemical coagulation and precipitation, and evaporation. We examined the validity of these methods and the behavior of ¹⁴C liquid in waste. The knowledge obtained in this study is important to develop effective removal methods for ¹⁴C in liquid waste.

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Volatilization of Ruthenium from Various Aqueous Solutions at Room Temperature

Hiroshi TAKESHITA, Kiyoko IMAI, Kazuo WATARI

1994 Volume 29 Issue 2 Pages 173-177
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.173

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Volatilization of radioruthenium from acidic or alkaline sample solutions at room temperature was studied. A sample solution containing radioruthenium is placed in a glass tube with ruthenium carrier and oxidizing agent. The mouth of the tube is covered with parafilm and the tube contents are stirred slowly, while the ruthenium is gradually oxidized to gaseous tetroxide. When contact with the tetroxide, parafilm surface was covered with insoluble black deposit of ruthenium.
The effects of elapsed time, concentration of ruthenium carrier, kinds of sample solutions and oxidizing agents on volatilization were studied.

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Intercomparison of Radon Measurement with Passive Method in Japan

Takao IIDA, Michikuni SHIMO, Keizo YAMASAKI, Siro ABE

1994 Volume 29 Issue 2 Pages 179-188
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.179

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Intercomparison exercises were performed during the period from January 1989 to September 1991 on passive ²²²Rn measurements at Critical Assembly Building of the Research Reactor Institute, Kyoto University (KUCA) and Nagoya University (NU). Most of the institutions in Japan which practiced passive ²²²Rn measurements participated in the exercises which were carried out in 4 rounds. Numbers of participating institution were 4, 6, 12 and 13 for the first, second, third and fourth rounds, respectively. The methods entered in the intercomparison was: (1) electrostatic collection method using solid-state nuclear-track detector (SSNTD), thermoluminescent dosimeter (TLD) and photodiode detector as detectors, (2) cup method with SSNTD in a filtered cup, and (3) are method using a bare SSNTD.
The round 1 intercomparison of 3-day exposure were performed in a room of KUCA of about 470 Bq·m^-3 that was evaluated using a flow-through ionization chamber. The average value for the 4 participating institutions was 430±38Bq·m^-3. For the second and third rounds, ²²²Rn concentrations with the ionization chamber were 56 and 47Bq·m^-3 in a preparation room of KUCA. The average concentrations obtained by passive methods for exposures of 39 and 58 days were 56.5±10.3 and 48.6±9.5Bq·m^-3 for the second and the third rounds, respectively. Fourth run was made on the campus of NU at outdoor ²²²Rn concentration of 3-7Bq·m^-3 that was measured with an electrostatic ²²²Rn monitor (ERM). The integrating ²²²Rn concentrations were 4-10kBq·m^-3·h for exposure of two months, 9-14kBq·m^-3·h for three months and 18-25kBq·m^-3·h for six months. The mean ratio of the measured values with passive monitors to ERM was 1.17±0.41.
Results of measurements agreed fairly well with those obtained with active methods, although standard deviations were rather large, especially in cup and bare methods.

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Evaluation on Collection Efficiency of Activated Carbon Fiber Filter for Radioactive Hydrogen Sulfide in Air Effluent Monitoring

Hiroshi KAMINAGA, Yoichi KAJIMOTO, Takaya OHNUKI, Akira ENDO, Yoshio I ...

1994 Volume 29 Issue 2 Pages 189-194
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.189

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Various kinds of ³⁵S-labeled compound are produced in the Radioisotope Production Laboratory at JAERI, and radioactive liquid waste containing ³⁵S that resulted from the productions is stored in the radwaste tanks. The air in these tanks is contaminated by gaseous ³⁵S and part of the air was exhausted from the stack as air effluent. Analysis by gas chromatography showed that the chemical form of ³⁵S gas was H₂S.
Radioactive concentration of H₂³⁵S gas in the air was measured by adsorbing it on activated carbon fiber filters (non-impregnated and TEDA-impregnated). Since the collection efficiency depends on collection condition, a method by using a ratio of the back side count rate of a filter to the front side one was developed to estimate the collection efficiency of the filter. Experimental results showed that the method is valid for the evaluation of collection efficiency.

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Variations of Irradiances by the Solar UVR Scattered in the Sky

Itsumasa URABE

1994 Volume 29 Issue 2 Pages 195-199
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.195

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A Preliminary Study on the Effects of Start Age of Uptake on Dose Assessment for Chronic Ingestion of Radionuclides

Kunihiko SHINOHARA

1994 Volume 29 Issue 2 Pages 201-205
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.201

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Analysis of the Optimum Arrangement of Man-power in the Radiological Safety Section of a University Using Analytical Tree Method

Yuko BESSHO, Tomoko KUSAMA

1994 Volume 29 Issue 2 Pages 207-211
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.207

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A Brief Introduction of ICRP Publication 62: “Radiological Protection in Biomedical Research”

Nobuhiko BAN

1994 Volume 29 Issue 2 Pages 213-216
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.213

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Present Status of Whole-Body Counters in Japan and the Discussions on Its Classification and General Requirements in the View of Standardization

Toshiso KOSAKO, Nobuyuki SUGIURA, Masafumi UCHIYAMA, Seiichi MIZUSHITA ...

1994 Volume 29 Issue 2 Pages 217-228
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.217

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The present status of whole-body counters are widely reviewed in the range of institutes, universities, hospitals or public health centers in the local governments and nuclear power plants. The basic characters of whole-body counters are summarized in the view of standardization, including the discussion on classification of devices, reference levels of radiation protection, detection limits, calibration methods and human phantoms.

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Note from Radiation Workers (Vol. 29, No. 2)

Nobuyuki SUGIURA, Kazuyoshi EDA, Toshiso KOSAKO

1994 Volume 29 Issue 2 Pages 239-243
Published: 1994
Released on J-STAGE: February 25, 2010

DOIhttps://doi.org/10.5453/jhps.29.239

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