• Journal of Radiation Protection and Research
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• v.23 no.4
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• pp.267-271
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• 1998

It is required to measure air density correction factor at the time of absorbed dose calibration or measurement. In general, thermometer and barometer are widely used for air density correction. However, this can be done using the radioactive check device with better accuracy. The measurements of air density correction were performed by using the radioactive check device, Unidos electrometer, and 0.6 cc Farmer-type ion chamber of PTW under the different environmental conditions. Above experiments were repeated with thermometer and barometer. By comparing the two methods, they were within the difference of 0.2 %. The overall uncertainty for the dose found in thermometer and barometer was 1.2 - 1.6 %, depending upon either one step or two, whereas the overall uncertainty for the radioactive check device was 1.02 %. This method may reduce the possible error which could occur when thermometer and barometer are not calibrated at regular basis.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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• v.6 no.4
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• pp.257-263
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• 2008

We analyzed the statistical properties for the conductive background fractures in the Low and Intermediate Level Waste(LILW) disposal site to conceptualize of its groundwater flow system. The background fractures were classified to fracture sets based on their trends and plunges that were obtained from the borehole logging data, and then the fracture transmissivity distribution was inferred from the fixed interval hydraulic test results. The fracture size distribution of each fracture set was estimated using the fracture density and fracture mapping data. To verify the analyzed results, we compared observed field data to simulated one from the DFN model that was constructed with the analyzed statistical properties of the background fractures, and they showed a good agreement.

• Proceedings of the Korean Nuclear Society Conference
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• 1995.05b
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• pp.827-832
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• 1995

한국원자력연구소 실증소각시설의 성능 및 운전성을 입증하기 위하여 방사성동위원소를 포함한 모의폐기물 및 원자력발전소 발생 방사성폐기물에 대한 시험소각을 실시하였다. 비휘발성인 $^{60}$Co 및 $^{54}$Mn의 거동은 비산재의 거동과 거의 유사하였으며 각각의 제염계수는 4.7 x $10^{5}$및 6.2 x $10^{5}$이었다. 반휘발성인 $^{137}$Cs의 경우에는 8$50^{\circ}C$ 및 $700^{\circ}C$의 다른 소각온도에서 각각 2.8 $\times$ $10^4$, 2.6 $\times$ $10^3$으로 소각온도의 의존성을 보여주었다. 원자력발전소에서 운반된 건조 방사성폐기물(DAW)에 대한 시험소각은 성공적으로 수행되었다. 총 베타/감마 방사능에 대한 제염계수가 1.1 $\times$ $10^{5}$이었으며 결과적인 연돌에서의 배출농도는 0.019 Bq/N㎥으로 기체상 배출물에 대한 최대허용농도를 만족시킬 수 있었다.수 있었다.

• The Journal of the Acoustical Society of Korea
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• v.13 no.2
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• pp.13-22
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• 1994

A theoretical model is studied to describe the sound radiation by the surface vibration of in-service tires. The tire is modeled as a circular ring model. The effects of normalized frequency and structrual loss factor are included. Through numerical integration of the sound pressure, the radiated sound power is calculated as a fuction of normalized frequency and structural loss factor. The basic sound radiation mechanism is shown to be the damped progressive wave field on the structure in the vicinity of the applied force. The results indicate that the potential sound reduction might be obtained if values of normalized frequency and structural loss factor are investigated.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.385-386
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.05a
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• pp.315-316
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.243-244
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• 2004

금속성 방사성폐기물을 제염하는 설비의 조건으로는 제염계수, 2차 폐기물 발생량, 모재의 회수가능성, 작업자의 안전성(원격조정) 등을 고려하여야 한다. 금속성 방사성폐기물의 오염제거 방법으로 습식제염 방법을 손쉽게 생각할 수 있으나 습식제염은 모재로부터 오염 물질을 선택적으로 제염이 불가능하고 강산 용액을 사용하므로 제염후 발생되는 2차 액체폐기물로 인해 최근 그 적용이 제한되고 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.411-412
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.381-382
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• 2010

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.11a
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• pp.245-246
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• 2009