• Proceedings of the Korean Institute of IIIuminating and Electrical Installation Engineers Conference
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• 2003.11a
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• pp.191-195
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• 2003

우리는 황토 조명등을 제작하여 원 적외선 발생 실험을 하였다. 실험에는 백열전구 200W, 실내온도 21도, 습도 38%의 조건에서 열화상실험과 TF-IR(적외선 분광방사 측정장치)에 의한 원적외선 방사한도를 측정하였으며, 그 결과 방사율 0.914와 방사에너지 6.23$\times$$10^2$ (w/$m^2$.$\mu\textrm{m}$) 가 얻어졌다. 이와 같은 결과로 황토조명등에서 원적외선이 발생한 것을 확인하였다.

• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.5 no.4
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• pp.3-7
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• 1991

This paper proposes a simplifying model for the calculation of the radiant flux and radiation energy in an RD(Radiation Dominated) arcplasma. Defects of the previous models are that the radiant flux and radition energy must be numerically solved by the three dimensional integration, and these calculations demand enormous computing time. These attribute to the global properties of radiation transfer. This paper suggests a simple calculation technique of radiation characteristics by considering the relation between the plasma states and the radiation transfer process and by the systematic tabulation of the relation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2003.11a
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• pp.15-20
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• 2003

During operation process of SIES(Selective ion exchange system) at Kori Unit 2, it was impossible to remove radionuclides such as ion form and Ag-110m, etc., because activated carbon and ion exchange resin of this system are fouled easily by suspended solids and oils in liquid radwaste that was flowed in this system. In this study, an experiment to improve quality of water which was flowed in SIES was performed. and design data of Scale-up pretreatment process were secured. Also, each module design for Microfiltration and Nanofiltration unit of the pretreatment process for SIES was performed.

• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.5 no.1
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• pp.40-45
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• 1991

This paper proposes a simplifying model for the calculation of the radiant flux and radiation energy in an RD (Radiation Dominated) arcplasma. Defects of the previous models are that the radiant flux and radition energy must be numerically solved by the three dimensional integration, and these calculations demand enormous computing time. Thses attribute to the global properties of radiation transfer. This paper suggests a simple calculation technique of radiation characteristics by considerig the relation between the plasma states and the radiation transfer process and by the systematic tabulation of the relation.

• Proceedings of the Korean Radioactive Waste Society Conference
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• 2009.06a
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• pp.95-96
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• 2009

• Proceedings of the Korea Institute of Fire Science and Engineering Conference
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• 2012.04a
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• pp.155-158
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• 2012

$CO_2$ 소화설비는 방호구역 내 적절한 설계농도를 확보하고 또한 일정 시간 유지해 주어야 충분한 소화성능을 발휘할 수가 있다. 따라서 시공 후에도 $CO_2$ 소화설비의 성능을 주기적으로 확인이 필요하다. 석유화학플랜트나 원자력발전소와 같은 국가 중요위험시설은 화재 발생시 대형피해가 발생할 수 있으므로 직접방사시험을 통해 소화성능을 검증할 필요가 있다. 본 연구는 국가 중요위험시설에 설치된 전역방출방식의 $CO_2$ 소화설비 중에서 표면화재 방호구역과 심부화재 방호구역을 각각 선정하여 $CO_2$ 소화설비의 소화성능을 검증해 보았다. 시험결과 표면화재와 심부화재 방호구역 모두 $CO_2$ 설계농도를 확보하고 있음을 확인하였으며, 심부화재의 경우 20분 이상 설계농도가 유지되었다. 본 연구를 통해 직접 방사시험 방법 및 판정방법을 소개하였으며, 국가 중요위험시설에는 직접 방사시험을 통한 소화설비 신뢰성 검증의 필요성을 제기하였다.

• 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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• 2006.06a
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• pp.164-165
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• 2006

• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.19 no.3
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• pp.16-18
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• 2005

• The Proceedings of the Korean Institute of Illuminating and Electrical Installation Engineers
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• v.15 no.1
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• pp.14-22
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• 2001