• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.06a
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• pp.238-239
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• 2006

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2006.11a
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• pp.307-308
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• 2006

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2007.11a
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• pp.329-330
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• 2007

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2016.05a
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• pp.95-96
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• 2016

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.437-438
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• 2004

원자력시설의 정상운영시 방사성물질이 기체 및 액체상의 형태로 소외로 배출되며, 일정기간별로 배출된 핵종별 총량을 이용하여 주민피폭선량 평가를 수행함으로써 규제요건의 준수 여부를 확인한다. 이러한 원자력시설 주변 주민피폭선량평가에 적용되고 있는 주요 입력자료인 음식물섭취자료 등은 1988년 원자력연구소의 현장조사, 실험, 문헌조사 등을 통하여 결정되었으나 시간이 지남에 따라 일부자료의 경우 최신경향을 반영할 수 있도록 개정이 요구된다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2004.06a
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• pp.225-225
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• 2004

원전 1차 냉각계통내 화학첨가제인 amine 또는 과산화수소를 사용하면서 $^{14}N$(n, P)$^{14}C$와 $^{17}O$(n, $\alpha$)$^{14}C$의 핵반응으로 생성된 $^{14}C$는 냉각수내에서 방사성 폐기물로 존재하게 된다. 이들 방사성 폐기물은 pH에 따라 다르지만 수용액상에서는 대부분 $CO_2$, $H_2CO_3$, ${HCO_3}^-$ 및 ${CO_3}^{2-}$로 존재하고, 나머지 약 20% 정도는 유기성 탄소로는 메탄이 존재하는 것으로 알려져 있다. 폐이온 교환수지 내에 존재하는 $^{14}C$는 시간이 경과함에 따라서 방향족 화합물로 이온교환이 발생할 수가 있다.(중략)

• Journal of Radiation Protection and Research
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• v.24 no.2
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• pp.101-108
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• 1999

The influence of the relative humidity, the temperature and the velocity of supply air on evaporation rate has been studied with non-boiling forced evaporation system in order to treat very low level radioactive liquid wastes produced from the decontamination and decommissioning activities. Experimental data on the evaporation rate have been obtained with the divers variables and experimental equation of air velocity was also obtained by the correlation of those data. The decontamination factor of this system was also obtained by the experimental data from a simulated liquid waste containing Cs-137 radio isotope ; $DF=10^4$. Since the commercial system will be operated for the treatment of the very low level radioactive liquid waste produced from decontamination & decommissioning of TRIGA Mark-II&III research reactor, the environmental assessment has been conducted to improve the operational safety. Exposure dose rate for an individual member of general public was assessed, and it showed that it was very lower than individual dose limits. The release of radioactivity of radioisotope material (Cs-137) to the environment was assessed, and result showed that it was $4.637{\times}10^{-14}\;{\mu}Ci/cc$.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.220-225
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• 2003

Generally, liquid radioactive wastes generated in nuclear power plant exist in powder form which do not contain moisture through the evaporating process of the Liquid Waste Management System and drying process of the Concentrated Waste Drying System. This powder form wastes are blended homogeneously with paraffin solidification agent and packed in metal drum to ensure its stability during handling and disposal. However, it was experienced that the powder form wastes were not blended homogeneously and separated into two layers in metal drum, on the other hand, a Portion of powder was adhered and solidified to the Inside parts of facility during the blending process. And the flaw of blending process above would come in case the mole ratio of Boron to Sodium in liquid radioactive wastes exceeds 0.2.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2008.11a
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• pp.275-276
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• 2008

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2010.05a
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• pp.249-250
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• 2010