• 대한방사선방어학회:학술대회논문집
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• 2010.04a
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• pp.110-111
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• 2010

• Journal of Radiation Protection and Research
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• v.38 no.4
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• pp.242-245
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• 2013

Monte Carlo method was applied to discriminate the external contamination on radiation workers in nuclear power plants for internal dose assessment generally used with a bed type scanning detector whole body counter. Korean voxel model with internal contamination was used to estimate the detection patterns of whole body scanning. Also, the BOMAB model with various external contamination was assumed to compare with detection of radionuclides inside the human body. From the comparison of detection efficiency between front and back side up, external contamination was easily distinguished.

• 대한방사선방어학회:학술대회논문집
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• 2009.11a
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• pp.96-97
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• 2009

• 대한방사선방어학회:학술대회논문집
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• 2011.04a
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• pp.168-169
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• 2011

• 대한방사선방어학회:학술대회논문집
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• 2009.04a
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• pp.246-247
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• 2009

• 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.

• Proceedings of the Korea Contents Association Conference
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• 2014.11a
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• pp.233-234
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• 2014

하지전신계측검사(low extremity teleography)에서 자세 변화에 따른 중요장기의 방사선량을 측정하고 영상을 비교 분석하여 검사방법에 따른 유용성을 알아보고자 하였다. 대상은 하지전신계측검사를 시행한 성인남자 10명을 대상하였고 촬영조건은 관전압 73 kVp, 관전류량 32 mAs, SID 180 cm로 설정하였다. 방사선량 측정은 란도 팬텀을 이용하여 수정체, 갑상선, 생식선 부위에 유리선량계(ion chamber)를 부착한 후 전후방향자세와 후전방향자세를 각각 5번씩 시행하여 부위별로 방사선량을 측정한 후 Paired T-test로 비교 분석 하였다. 영상평가는 전후방향자세와 후전방향자세를 시행한 영상을 blind test를 실시하여 5점 척도로 평가하였다. 결과적으로 전후방향자세검사에 비해 후전방향자세검사가 수정체 약 6%, 갑상선 약 6%, 생식선에 미치는 방사선량을 약 27% 감소시킬 수 있으며 영상평가에서도 두 그룹 간에 큰 차이가 없어, 하지전신계측검사에서 전후방향자세검사보다 후전방향자세검사가 유용할 것으로 사료된다.

• 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.

• Journal of Radiation Protection and Research
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• v.34 no.3
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• pp.121-128
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• 2009

During the maintenance period at Korean nuclear power plants, internal exposure of radiation workers occurred by the inhalation of $^{131}I$ released to the reactor building when primary system was opened. The internal radioactivity of radiation workers contaminated by $^{131}I$ was immediately measured using a whole body counter and the whole body counting was performed again after a few days. In this study, the intake estimated from the record history of entrance to radiation control areas and the measurement results of air sampling for $^{131}I$ in those areas, were compared with that from the results of whole body counting. As a result, it was concluded that the intake estimation using whole body counting and air sampling showed similar results.

• 대한방사선방어학회:학술대회논문집
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• 2011.11a
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• pp.308-309
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• 2011