• Title/Summary/Keyword: 세슘 동위원소

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Cesium Radioisotope Measurement Method for Environmental Soil by Ammonium Molybdophosphate (환경토양에서 몰리브도인산 암모늄을 이용한 세슘 동위원소 평가방법)

  • Choe, Yeong-hun;Seo, Yang Gon
    • Clean Technology
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    • v.22 no.2
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    • pp.122-131
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    • 2016
  • Caesium radioisotopes, 134Cs and 137Cs which come from the atmospheric nuclear tests and discharges from nuclear power plants, are very important to study artificial radioactivity. In this work, in order to lower the minimum detection activity (MDA) we investigated environmental radioactivity according to the Environment Measurement Laboratory procedure by 137Cs and 134Cs which is similar to chemical and environmental behaviors of 137Cs. The environmental soils in high mountain areas near nuclear power plant were collected, and an Ammonium Molybdophosphate (AMP) precipitation method, which showed high selectivity toward Cs+ ions, was applied to chemically extract and concentrate Caesium radioisotopes. Radioactivity was estimated by a gamma-ray spectrometry. In gamma energy spectrum, with an increasing of 40K radioactivity, it increased the MDA of 134Cs and 137Cs. Therefore, if the natural radionuclides were removed from the soil samples, the MDA of Caesium may be reduced, and the contents of 137Cs of in the environmental soils can effectively be estimated. In the standard soil sample of Korea Institute of Nuclear Safety, radioactivity of 40K was removed more than 84% on average, and the MDA of 134Cs was reduced 2 times. The content of 137Cs was recovered over 84%. On the other hand, in environmental soils, AMP precipitation method showed removal ratio of 40K up to 180 times, which reduced the MDA about 5 times smaller than those of Direct method. 137Cs recovery ratio showed from 54.54% to 70.06%. When considering the MDA and recovery ratio, AMP precipitation method is effective for detection of Caesium radioisotopes in low concentration.

RI 이리듐-192의 이용현황과 전망

  • 류성렬
    • Nuclear industry
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    • v.15 no.10 s.152
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    • pp.73-78
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    • 1995
  • 이리듐-192(lr-192)는 각종 형태의 암조직의 특성에 맞게 변형하여 적절히 사용되는 특수치료용 동위원소로서, 반감기가 74일로 짧으며 에너지도 낮아 보관$\cdot$관리가 용이하고, 금속 철선 형태로 제작되어 인체내의 암조직에 바늘상태로 자입하는데 편리하게 사용되므로 근접치료에 가장 보편적으로 사용된다. 또한 라듐(Ra-226)이나 세슘(Cs-137)과 달리 시술하는 의료진의 방사선피폭에 전혀 문제가 없다. 원자력병원 연구팀은 최근 이를 이용, 안구 적출없이 안구암흑색종을 치료하는 신기술을 개발한 바 있다.

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A Study on the Decontamination of Cs-137 and Sr-90 Contained in the Liquid Radioactive Waste Discharged from the Spent Fuel Storage Tank Using Microalgae (미세조류를 이용한 사용후핵연료 저장조에서 배출되는 방사성 폐액에 함유된 Cs-137 및 Sr-90 제염에 관한 연구)

  • Kim, Tae Young;Park, Hye Min;Song, Yang Soo;Lee, Un Jang
    • Resources Recycling
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    • v.31 no.5
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    • pp.20-25
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    • 2022
  • In this study, the applicability of microalgae was evaluated for eco-friendly decontamination of cesium-137 (Cs-137) and strontium-90 (Sr-90), which are radioactive nuclides contained in radioactive waste. The monolithic radioactive solution used in the experiment was manufactured at a concentration of 1.5 Bq/mL Cs-137 and 1.0 Bq/mL Sr-90 by diluting a standard radioactive solution and distilled water. This experiment used two types of microalgae, Chlorella Vulgaris was used for Sr-90 decontamination and Hematococcus pluvialis for Cs-137 decontamination. The experimental method is to put the microalgae cultured for 2 weeks into a bottle with a semi-permeable membrane, and then put the bottle in which the microalgae was put into the manufactured radioactive solution, so that the microalgae and the radioactive solution react through the semi-permeable membrane for 48 hours. For the radioactivity concentration analysis of each sample, a gamma-ray nuclide analyzer was used for Cs-137, a γ-ray isotope, and a Liquid Scintillation Count(LSC) was used f or Sr-90, a β-ray isotope. As a result of the experiment, it was confirmed that about 88.0 % of Cs-137 and about 89.7 % of Sr-90 could be decontaminated, and about 98.6 % of Sr-90 was finally able to be decontaminated by the two-stage decontamination method.

The Development of a Multi-Purpose Irradiator and the Characteristic of Dose Distribution (다목적 방사선 조사장치 개발 및 선량분포특성)

  • Lee, Dong-Hoon;Ji, Young-Hoon;Lee, Dong-Han;Kim, Yoon-Jong;Hong, Seung-Hong
    • Journal of the Institute of Electronics Engineers of Korea SC
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    • v.39 no.6
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    • pp.42-48
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    • 2002
  • The design, construction and performance test of a convenient multi-purpose irradiator is described. A multi-purpose irradiator using Cesium-137 has been developed for studies of low dose radiation effects in biology and for calibration of Thermo Luminescent dosimeter(TLD). During the operation, three rods of radioactive material which are 10cm in length revolve 180 degrees and irradiate biological samples, or TLD, and return to their shielded position, after the programmed time. A programmable Logic Controller(PLC) controls the sequence of operation, interlock, motor rotation and safety system. The rotation speed of biological samples can vary up to 20 RPM. A real time monitoring system was also incorporated to check and control the operation status of the irradiator. The capacity of the irradiation chamber was 4.5 liters. The isodose distribution at arbitrary vertical planes was measured by using film dosimetry. The dose-rate was 0.13 cGy/min in air and 0.11 cGy/min in water equivalent material in the case of Cesium-137. Range of activity was 2 Ci. The homogeneity of dose distribution in the chamber was ${\pm}$7%. The actual radiation level on the surface was within permissible levels. The irradiator had a maximum 0.35 mR/min radiation leakage on its surface.