• 대한핵의학회:학술대회논문집
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• 1971.11a
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• pp.88.3-88.3
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• 1971

• Nuclear Engineering and Technology
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• v.54 no.8
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• pp.3017-3026
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• 2022

The ¹³¹Cs radioisotope with a short half-life time and high average radiation energy can treat the cancer effectively in prostate brachytherapy. The typical ¹³¹Cs production processes have a separation step of the cesium from ¹³¹Ba to obtain a high specific radioactivity. Herein, we suggested a novel ¹³¹Cs separation method based on the Ba²⁺ adsorption of alginate beads. It is necessary to reduce the affinity of alginate beads to cesium ions for a high production yield. The carboxyl group of the alginate beads was replaced by a sulfonate group to reduce the cesium affinity while reinforcing their affinity to barium ions. The modified beads exhibited superior Ba²⁺ adsorption performances to native beads. In the fixed-bed column tests, the saturation time and adsorption capacity could be estimated with the Yoon-Nelson model in various injection flow rates and initial concentrations. In terms of the Cs elution, the modified alginate showed better performance (i.e., an elution over 88%) than the native alginate (i.e., an elution below 10%), indicating that the functional group modification was effective in reducing the affinity to cesium ions. Therefore, the separation of cesium from the barium using the modified alginate is expected to be an additional option to produce ¹³¹Cs.

• Journal of Radiation Protection and Research
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• v.48 no.3
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• pp.131-143
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• 2023

Background: This study examined the detection limit of thyroid screening monitoring conducted at the time of the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident in 2011 using a Monte Carlo simulation. Materials and Methods: We calculated the detection limit of a NaI(Tl) survey meter to measure ¹³¹I accumulation in the thyroid gland of children. Mathematical phantoms of 1- and 5-year-old children were developed in the simulation of the Particle and Heavy Ion Transport code System code. Contamination of the body surface with eight radionuclides found after the FDNPP accident was assumed to have been deposited on the neck and shoulder area. Results and Discussion: The detection limit was calculated as a function of ambient dose rate. In the case of 40 Bq/cm² contamination on the body surface of the neck, the present simulations showed that residual thyroid radioactivity corresponding to thyroid dose of 100 mSv can be detected within 21 days after intake at the ambient dose rate of 0.2 µSv/hr and within 11 days in the case of 2.0 µSv/hr. When a time constant of 10 seconds was used at the dose rate of 0.2 µSv/hr, the estimated survey meter output error was 5%. Evaluation of the effect of individual differences in the location of the thyroid gland confirmed that the measured value would decrease by approximately 6% for a height difference of ±1 cm and increase by approximately 65% for a depth of 1 cm. Conclusion: In the event of a nuclear disaster, simple measurements carried out using a NaI(Tl) scintillation survey meter remain effective for assessing ¹³¹I intake. However, it should be noted that the presence of short-half-life radioactive materials on the body surface affects the detection limit.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.377-385
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• 2004

The quantity of radioactive waste generated from HANARO operation for the years of 1996 to 2003 has been analysed. It was found that the solid waste of $72, 999{\ell}$ and liquid waste of $263, 576{\ell}$ have been generated for the past 8 years. The amounts of Ar-41, I-131 and H-3 exhausted to the environment were 1, 225.6 Ci, 1.612E-2 Ci and 210 Ci, respectively.

• The Korean Journal of Nuclear Medicine
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• v.5 no.1
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• pp.71-76
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• 1971

7 laboratories located in Seoul were surveyed for the standardization of radioiodine thyroid uptake test in Korea. The result revealed that the currently utilized methods are almost standardized now, when the reference standard is IAEA recommendation method, 1962. Mean 24 hour uptake of thyroidal $^{131}I$ in Korean euthyroids is $31.6{\pm}8.80%$, and no significant interlaboratory differences are noticed. These results were caused probably by the late introduction of detector facilities into Korea after the appearance of publication of IAEA recommendations.

• The Korean Journal of Nuclear Medicine
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• v.26 no.1
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• pp.151-154
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• 1992

갈색종은 비교적 드문 종양으로 다발성으로 생기는 경우는 더욱 드물다. 갈색종은 수술로 90%이상 완치 가능한 질환이므로 수술전 종양의 위치와 범위를 정확히 확인하는 것 이 매우 중요하다. 저자들은 최근 파동하는 고혈압을 주소로 내원한 33세 남자환자에서 복부전산화 단층촬영술상 우측부신의 종양만을 확인할 수 있었으나, $^{131}I-MIBG$ 신티그라피에서는 우측 부신의 병소외에 골반강 내에 또다른 병소가 발견되어 골반강 전산화 단층촬영술을 추가로 시행하였고 이어 수술로써 확진된 이중병소의 갈색종 1예를 보고하는 바이다.

• Proceedings of the Korean Nuclear Society Conference
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• 2003.05a
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• pp.341.2-341.2
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• 2003

• Journal of Drive and Control
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• v.7 no.3
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• pp.2-6
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• 2010

• Proceedings of the Korean Society of Applied Pharmacology
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• 1996.04a
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• pp.238-238
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• 1996

각종 동물 및 인체 신장 유래 DHP-I에 의한 DA-1131, imipenem(IPM) 및 meropenem(MEPM)의 속도 상수를 측정한 결과, DA-1131은 동물종에 관계없이 가장 안정성이 큰 결과를 나타내었고, 인체 DHP-I에 대한 Vmax/Km 값이 IPM의 21.9%로 관찰되어 IPM보다 하위 기질인 것으로 확인되었다. DA-1131, IPM/CS 및 MEPM/CS의 20mg/kg투여 후의 혈중농도 반감기(T$_{1}$2/)는 각각 11.4분, 8.9분, 10.3분이었으며, 1$\mu\textrm{g}$/$m\ell$ 이상의 혈중농도룰 유지하는 시간은 66.6 분, 55.9 분, 63.1 분이었다. DA-1131, DA-l131/CS, IPM/CS, MEPM 및 MEPM/CS의 40 mg/kg 투여 후 24시간 동안의 뇨중 배설율은 57.9 %, 61.3%, 22.6 %, 11.3% 및 65.9%이었으며, 각 약물을 40 mg/kg 투여 15분 후 DA-ll3l의 폐중 농도는 11.2$\mu\textrm{g}$/g으로 DA-l131/CS, IPM/CS 및 MEPM/CS와 비슷한 결과를 나타내었으며 T/P ratio도 DA-1131, DA-l131/CS, IPM/CS 와 MEPM/CS 투여군에서 거의 동일한 것으로 확인되었다. 신장중 농도는 DA-1131 과 DA-l131/CS의 경우 29.l$\mu\textrm{g}$/g 및 34.2$\mu\textrm{g}$/g으로 큰 차이를 나타내지 않았으나, IPM/CS, MEPM 및 MEPM/CS 투여군에 비하여는 높은 결과로 나타났고 T/P ratio도 DA-1131과 DA-l131/CS 투여군이 IPM/CS, MEPM 및 MEPM/CS 투여군보다 놓은 것으로 확인되었다.

• Journal of radiological science and technology
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• v.41 no.2
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• pp.135-140
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• 2018

In this study, the dose of antimony shielding sheet was measured and the shielding rates according to the distance between the radioisotopes and the detector was analyzed according to the type of $^{99m}Tc$, $^{18}F$, $^{201}Tl$, $^{131}I$, $^{123}I$ using the antimony shielding sheet. The detector was used with an inspector. Six sheets of 0.25 mmPb were prepared with 20 cm width and length. Measurement results using $^{99m}Tc$, $^{201}Tl$, and $^{123}I$ showed that as the thickness of the sheet became thicker, the farther the distance from the source to the sheet was, the smaller the transmitted dose amount was measured. It was analyzed that a thickness of 1.50 mm or more was required to obtain a shielding rates of 90% or more. In the experiments of $^{18}F$ and $^{131}I$, the dose value was highest when 0.25 mm sheet was used, and the shielding rates was negative, unlike the results of other radioisotopes. Since $^{201}Tl$ are used when using antimony sheet and $^{18}F$ and $^{131}I$ have no shielding effect, it is thought that it is effective to reduce dose by repeating training and simulation training so that work can be done in a short time.