• Journal of Radiation Protection and Research
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• v.26 no.3
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• pp.149-154
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• 2001

Calculational models to evaluate radiation doses resulting from the medical use of high energy beta-ray sources are presented. The radioactive sources considered are Sr-90/Y-90 used as ophthalmic applicator, Re-188 used for treating restenosis of coronary artery, and Ho-166 used for treating hepatic tumors. Typical therapeutic situations which might induce relatively high radiation doses the medical person involved were considered to compute by using MCNP-4C Monte Carlo code the radiation doses. The calculation results suggest that for all of the cases considered, the evaluated radiation doses are negligible compared to the dose limits. It is also found that the effect of Bremsstrahlung radiations on the total dose is insignificant, and hence the conventional lead gown is also effective in shielding beta-rays.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.23-27
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• 1996

$\beta$-선 흡수선량의 1차 표준이 확립되지않은 상황에서 측정표준이 이미 확립된 외국의 표준기관에서 검증되어 도입된 $\beta$-선 흡수선량 조사시설에 대해 ISO-6980에서 명시한 항목에 대해 성능실험을 수행하였고, 외삽형전리함을 사용하여 측정된 이온화전류로 부터 흡수선량률을 재평가하여 외국의 검증결과와 비교하였다. 조사시설의 성능실험 결과 Sr$^{90}$ +Y$^{90}$ 선원에 대해 선원으로부터 30cm거리에서 빔 균일도, 제동복사선 기여도 및 $\beta$-선 최대잔여에너지가 기준에 적합한 것으로 나타났다. 그리고 흡수선량 평가결과는 '96. 4. 1을 기준으로하여 20 $^{\circ}C$,1기압에서 2.686 ($\pm$2.73%)$\mu$Gy/sec로 외국표준기관의 측정치와 1.8%이내에서 일치하는 것으로 나타났다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.63-68
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• 1996

열형광 선량계(TLD)를 사용한 피부 선량평가는 베타선의 에너지를 구분함으로 정확히 평가된다. 이는 차폐체에 의한 감쇄효과를 이용하는 방법으로 본 논문에서는 7개의 두께가 다른 알루미늄 차폐체를 사용하였고, TLD로는 미국 Teledyne Isotopes사의 LiF$_{7}$ 선량계를 채택하였다. 비상 베타 선량계의 베타선에 대한 특성실험을 위해 한국 원자력연구소가 확보 하고 있는 PTB 표준선원인 $^{90}$ Sr/ $^{90}$ Y (E$_{max}$=2.27MeV, E$_{avg}$=0.8MeV), $^{204}$Tl(E$_{max}$=0.76MeV, E$_{avg}$=0.26MeV), $^{147}$ Pm (E$_{max}$= 0.225MeV, E$_{avg}$=0.06MeV)에 대한 조사를 하였다. 이런 결과로 비상 베타 선량계의 표준 베타선원에 대한 보정계수와 소자별 반응비를 구할 수 있었고, 이것을 이용하여 미지의 베타선원에 대하여 정확한 선량평가를 하기위한 알고리즘을 개발하였다.

• Nuclear Engineering and Technology
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• v.5 no.3
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• pp.240-248
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• 1973

The present report concerns measurement of environmental radioactivity in the Ko-ri nuclear power plant site area. Gross beta measurements have been performed on soil, water, pine needle, and fallout samples collected during the period of December 1970-November 1972. Radioactivities of Strontium-90 and Cesium-137 have been measured by radiochemical analyses on samples of vegetables and marine products collected in 1972. Apparent seasonal variations and overall decrease by the year was also observed from the results of soil, pine needle, and fallout sample measurements respectively.

• Journal of Radiation Protection and Research
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• v.28 no.3
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• pp.173-182
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• 2003

A prototype liquid scillatillator system for measurement of multiple beta-labeled mixtures was developed and its characteristic was investigated. The signal processing system consists of two photomultiplier tubes and the coincident count circuit. The characteristic of the system was analyzed using 4 beta-labeled samples $(^3H,\;^{14}C,\;^{36}Cl\;and\;^{90}Sr)$. Beta spectra from the samples were obtained without radiation shielding, and the detection limits for each nuclides were estimated based on the spectra. The estimated detection limits were compared to the legal regulation values. It is found that the liquid radioactive nuclides are detectable well below the legal regulation values.

• Fire Science and Engineering
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• v.19 no.2 s.58
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• pp.75-80
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• 2005

This dissertation is about the development of PTC(Positive Temperature Coefficient) thermistor by composition method. A multilayer-type PTC samples were fabricated under optimal conditions after setting the experimental composition equation as $(0.90Ba+0.05Sr+0.05Ca)TiO_3+0.01TiO_3+0.01SiO_2+0.0008MnO_2+0.0018Nb_2O_5$ and their testing results were analyzed. The fabrication method of SMD(Surface Mounted Device) multilayer -type sample based on the composition ratio has the advantages in lowering its resistivity at room temperature, considerably, and increasing maximum current level, as needed. Although there is a disadvantage of peak resistivity drop by the multilayer, causing the increasement of thermal capacity. and thereby, increasing the switching delay time, a high applying voltage can increase the peak resistivity and shorten the switching delay time. The voltage-current characteristic showed that the more multilayers increased the initial maximum current and the transition voltage that increased the resistivity abruptly according to the curie point. The element it could be applied with the sensor for the fire detector.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.2 no.1
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• pp.35-40
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• 2004

Final disposal of radioactive waste generated from Nuclear Power Plant (NPP) requires the detailed information about the characteristics and the quantities of radionuclides in waste package. Most of these radionuclides are difficult to measure and expensive to assay. Thus it is suggested to the indirect method by which the concentration of the Difficult-to-Measure (DTM) nuclide is estimated using the correlations of concentration - it is called the scaling factor - between Easy-to-Measure (Key) nuclides and DTM nuclides with the measured concentration of the Key nuclide. In general, the scaling factor is determined by the log mean average (LMA) method and the regression method. However, these methods are inadequate to apply to fission product nuclides and some activation product nuclides such as 14$^{C}$ and 90$^{Sr}$ . In this study, the artificial neural network (ANN) method is suggested to improve the conventional SF determination methods - the LMA method and the regression method. The root mean squared errors (RMSE) of the ANN models are compared with those of the conventional SF determination models for 14$^{C}$ and 90$^{Sr}$ in two parts divided by a training part and a validation part. The SF determination models are arranged in the order of RMSEs as the following order: ANN model

• Progress in Medical Physics
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• v.12 no.2
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• pp.141-146
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• 2001

It is well known that assurance of the radiation therapy needs for an accuracy of $\pm$ 5 % in the delivery of an absorbed dose to target volume. Therefore, the dose evaluation of brachytherapy source and/or linear accelerate beam must be a stability with accuracy. In an advanced country, they recommended to use the radioactive check source for reference air ionization chamber for a stable response of radiation field chamber. In this experiments, the radioactive source Sr-90 and PR-05 air ionization chamber were used for standard source and reference ion chamber. The response of reference ion chamber showed as an 1.000$\pm$ 0.010 uncertainty for 10 years long and the evaliuation f dose discrepancy of clinical field ion chamber showed as 0.997 $\pm$0.011 in a $^{60}$ Co brachytherapy soruce. In our experiments, we can assuarance the long halflife standard source is reliable to preserve the calibration factor of reference chamber in stability.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.15 no.3
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• pp.281-299
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• 2017

The inventory management of radionuclides is essential for the safe management of disposal facilities. In this study, we compared the activity of dry active waste predicted using the generated waste data and that measured for the accepted waste in the disposal facility. For very low level waste, the measured activity was higher than the predicted activity for $^{137}CS$, $^{90}Sr$, $^{99}Tc$ and $^{129}I$. In low level waste, the predicted activity was higher than the measured activity for all radionuclides. We also evaluated the variation in the predicted quantity and total activity of each level of dry active waste through a sensitivity analysis on a scaling factor. This result will contribute to the construction of a Safety Case and safe operation of disposal facilities.

• Journal of Radiation Protection and Research
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• v.26 no.4
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• pp.375-384
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• 2001

It is possible to count and perform quench correction on two ${\beta}$ -label samples so long as the maximum ${\beta}$-energies are sufficiently different. However, when 4he conventional technique is applied to the radioassay of a mixture of more than three nuclides, the reliability of the activities determined is considerably reduced, resulting from the large overlapping of liquid scintillation pulse height distributions of each nuclide. A technique that allows the activities of multiple ${\beta}$-labeled samples to be radioassayed was proposed by using the least square method. The technique was applied to mixture samples of $^3H,\;^{14}C,\;^{36}Cl$, and $^{90}Sr$. The analytical values were in good agreement with the reference values within 7% relative error.