• Proceedings of the Korean Society of Disaster Information Conference
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• 2023.11a
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• pp.224-225
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• 2023

방사능재난 시 주민의 방사선 피폭을 최소화하기 위하여 대피 및 소개가 신속하게 이루어져야 한다. 주민이 휴대용 방사선 계측기를 통하여 방사능 오염 발생을 감지해 사전에 신속히 대피할 수 있다면, 방사능재난 대응에 기여할 수 있을 것으로 사료된다. 본 논문에서는 방사능재난 시 주민이 사용하기 용이한 방사선 계측기를 제시하고, 향후 보완하여야 하는 사항에 대해 검토하였다.

• 전기의세계
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• v.10
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• pp.62-71
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• 1963

공업계측분야에 대한 계수기술은 최근획기적인 발전을 거두고있다. 계수화된 계측기는 측정정도에 있어서 개인차나 오산이 없으므로 과거의 눈금식의 계측방식은 이로 대치되어 갈것인데 그 계측 가능한 속도에 있어서 종래의 진공관보다 Transistor식이 되면 훨씬 고속도까지도 계수가 쉽게 되고 장치 및 계수표시용소비전력도 개량되어가고 있다. 이러한것이 되므로서 높은 주파수측정, 짧은 시간측정은 물론이고 전기적인 진폭의 크기를 Analog to Digital 변환기로서 정밀도가 높은 계측을 가능하게 하고 특히 방사능 측정에 있어서 종래의것보다 더 고속화되므로서 방사능의 완전한 성질을 파악할 수 있을 것이다. 그것은 1Cure의 방사능이 3.7*$10^{10}$dps의 붕괴수를 갖고 있으나 현재는 약 2.8*$10^{7}$ cps정도의 계측이 가능할 따름이다. 따라서 계측속도를 더 향상시키므로서 강한 방사능계측도 가능하게 된다. 이러한 고속계수문제의 해결을 하기 위하여 Transistor회로로서 두가지면으로 추구되고 있다. 그 하나는 고속도용 Transistor자체의 개발이며 또하나는 회로적인 개량연구이다. 여기서는 후자에 관해서만 생각하고, 거기에 적합한 Transistor를 얻었을때의 설계기준과 기본적인 실험결과에 관해서 논하기로 한다.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2022.05a
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• pp.459-461
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• 2022

In this paper, we propose a measurement system for measuring radioactivity detected in an indoor environment. This is to measure and prevent radiation generated in various spaces such as general house, workplace, and research institutes. Multi-radioactivity sensors are used to measure multiple spaces simultaneously. The measured radioactivity data is transmitted to the PC in real time through ZigBee and monitored. Even with a small amount of radioactivity, it is considered that it must be installed in a place where radiation exposure is expected, such as a laboratory or workplace, for prevention from chronic radiation syndrome.

• Journal of Radiation Protection and Research
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• v.34 no.1
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• pp.37-42
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• 2009

Whole body counters (WBCs) are used to monitor radiation workers for internal contamination of radionuclides at domestic nuclear power plants (NPPs). A WBC is a scintillation detector using sodium iodide (NaI) and provides the identification of inhaled radionuclide and the measurement of its internal radioactivity in a short time. However, it is often possible to estimate external contamination as internal contamination due to radionuclides attached to the skin of radiation workers and this leads to an excessively conservative estimation of radioactive contamination. In this study, several experiments using a WBC and the Korean humanoid phantom were performed to suggest the more systematic method of discrimination between external and internal contamination. Furthermore, a WBC geometry experiment was conducted to suggest the optimal WBC geometry in consideration of deposited areas inside the body for dominant radionuclides at NPPs. The procedure of measurement and estimation of internal radioactivity for radiation workers at NPPs was improved on the basis of experimental results. Thus, it is expected to prevent from estimating internal exposure dose conservatively owing to the application of accurate whole body counting program to NPPs.

• Journal of Radiation Protection and Research
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• v.23 no.2
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• pp.65-74
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• 1998

One of the important things in low level radioactivity measurement is determination of the optimized counting time. Counting strategy has to be established, in order to count the radioactivity of the sample by condition of optimized measurement. There were three kinds of counting strategies in this report ; about fixed time, about fixed count, to compared sample, background, and reference level. The best of them was satisfied rendition to give about condition of instrument and process, as an example, efficiency of detector, counter capacity, maximum and average background count rate of counter, reference level and limit of derision and detection, etc. Therefore, we can decide the optimized counting time in the screening and monitoring. And we can save the time for courting the sample of course the data of count will be counted by optimized accuracy finally, in rountine measurement of radioactivity these strategies will be used available.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.419-424
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• 2004

Various radiation counters have been using to determine radioactivity of radwastes for disposal. A radiation counting system was set up using a radiation detector chosen in this study and its stability was investigated through the periodic determination of background and counting efficiencies in accordance with a quality control program to increase the confidence level. The average background level for the $\gamma$-spectrometer was 1.59 cps and the average counting level for the standard sample was 45248 Ops within $2{\sigma}$ confidence levels. The average alpha background level for the low background ${\alpha}{\beta}$ counting system was 0.31 cpm and the efficiency for alpha counting was 34.38%. The average beta background level for the ${\alpha}{\beta}$ counting system was 1,30 cpm and the efficiency for beta counting was 46.5%, The background level in the region of 3H and 14C for the liquid scintillation counting system was 2.52 and 3.31 cpm and the efficiency for alpha counting was 58.5 and 95.6%, respectively. The minimum detectable activity for the$\gamma$-spectrometer was found to be 3.2 Bq/$m\ell$ and 3.8 Bq/$m\ell$ for the liquid scintillation counter, and 20.5 and 23.0 Bq/$m\ell$, respectively for the $\alpha$ and $\beta$ counting system.

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.108-109
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• 2009

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.124-125
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• 2011

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05a
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• pp.835-840
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• 1995

핵물질의 화학적분리 및 정제를 위한 용매추출실험의 농도분석에 사용될 수 있는 감마방사능 계측장치를 제작하고 기계적 성능 및 원격작동 시험을 하였다. 계측장치의 모든 구동부분은 공압으로 작동되며 우라늄시료를 분석한 결과 0∼250g/L의 농도범위에서 방사능세기와 일정한 상관관계를 나타내었다.

• Journal of Radiation Protection and Research
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• v.39 no.1
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• pp.1-6
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• 2014

A whole body counter (WBC) is used in nuclear power plants (NPP) to identify and measure internal radioactivity of workers who is likely to ingest or inhale radionuclides. WBC has several counting geometry, i.e. the thyroid, lung, whole body and gastrointestinal tract, considered with the location where radionuclides are deposited in the body. But only whole body geometry is used to detect internal radioactivity during whole body counting at NPPs. It is overestimated internal exposure dose because this measured values are indicated as the most conservative radioactivity values among the them of others geometry. In this study, experiments to measure radioactivity depending on the counting geometry of WBC were carried out using a WBC, a phantom, and standard radiation sources in order to improve overestimated internal exposure dose. Quantitative criteria, could be selected counting geometry according to ratio of count rates of the upper and lower detectors of the WBC, are provided through statistical analysis method.