• Proceedings of the Korean Vacuum Society Conference
• /
• 2004.02a
• /
• pp.162-162
• /
• 2004

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.17 no.2
• /
• pp.203-212
• /
• 2019

Disposal nonconformity of radioactive wastes refers to radioactive wastes that need to be treated, solidified and packaged during operation or decommissioning of NPPs, and are typically exemplified by particulate radioactive wastes with dispersion characteristics. These wastes include the dried powders of concentrated wastes generated in the process of operating NPPs, slurry and sludge, various powdered wastes generated in the decommissioning process (crushed concrete, decontamination sludge, etc.), and fine radioactive soil, which is not easy to decontaminate. As these particulate wastes must be packaged so that they become non-dispersive, they are solidified with solidification agents such as cement and polymer. If they are treated using existing solidification methods, however, the volume of the final wastes will increase. This drawback may increase the disposal cost and reduce the acceptability of disposal sites. Accordingly, to solve these problems, this study investigates the pelletization of particulate radioactive wastes in order to reduce final waste volume.

• Composites Research
• /
• v.35 no.2
• /
• pp.69-74
• /
• 2022

In this study, the conductive paste used in a wide range such as wiring in the electronic packaging field, the automobile industry, and electronic products is manufactured under various process conditions due to the simplicity of the process, and then the thermal, mechanical, and electrical characteristics are analyzed and simulation studies are conducted to optimize the process. to establish the conditions of the conductive paste manufacturing process. First, a conductive paste was prepared by setting various types of binder resin, an essential component of the conductive paste, and characteristics such as thermal conductivity, tensile strength, and elongation were analyzed. Among the binder resins, the conductive paste applied with a flexible epoxy material had the best physical properties, and a simulation study was conducted based on the physical property data base of the conductive face. As a result of the simulation, the best physical properties were exhibited when the Ag flake volume fraction was 60%.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.351-351
• /
• 2004

원자력연구소에서는 PWR 사용후핵연료를 건식 개질함으로써 관리 부피를 줄이고 안전상에 문제를 일으키는 고방사성 핵종인 세슘과 스트론튬 등을 선택적으로 제거하여 방사능 및 냉각부하를 줄일 수 있는 사용후핵연료 차세대관리 공정개발에 대한 연구를 수행하고 있다. 이는 세라믹 형태의 PWR 핵연료를 금속으로 전환시켜 관리하는 방법으로 금속전환체는 PWR 사용후핵연료와 비교하여 체적, 방사능 및 발열량을 약 1/4로 줄일 수 있는 이점이 있다.(중략)

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.349-349
• /
• 2004

차세대관리 종합공정(Advanced spent fuel Conditioning Process)은 사용후핵연료의 안전하고 효율적인 관리를 위하여 제시된 건식처리공정으로 사용후핵연료를 금속으로 전환하고, 고발열성 핵종(Cs, Sr)을 효율적으로 제거하여 사용후핵연료의 부피, 발열량 및 방사선의 세기를 최대 1/4까지 감소시키고, 처분용기의 소요량과 처분장의 소요면적을 1/2 이상으로 축소함으로서 처분 안전성과 경제성을 높일 수 있는 장점으로 인해 연구개발 중에 있으며, 이의 실증시험 수행을 위하여 ${\alpha}-{\gamma}$ type의 핫셀을 건설 중에 있다.(중략)

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05b
• /
• pp.421-426
• /
• 1998

원자력발전소에서 발생되는 방사성 세탁폐액의 처리연구틀 위하여 100L/h 처리용량의 오존접촉조-활성탄탑-역삼투막-이온교환수지탑의 복합공정을 제작하고 영광 4호기에 설치하여 단위공정별 성능실험을 수행하였다. 오존에 의한 세제 제거율은 약 50％로 나타났으며, 활성탄탑을 거친후에는 거의 모든 유기물이 제거되었다. 역삼투막에 의하여 방사성핵종 제거율 설험은 원수의 부피를 1/10로 줄이는 데까지 농축도를 증가시키면서 수행하였는데, 농축도에 따라 핵종제거율이 약간 감소하는 경향은 있었으나 대체적으로 99% 정도의 제거율을 나타내었다.

• Proceedings of the Membrane Society of Korea Conference
• /
• 1998.10a
• /
• pp.93-95
• /
• 1998

1. 서론 : 폴리이미드계 고분자는 기계적 성질과 내열성이 우수한 고분자 소재이다. 일반적으로 기체분리막으로서의 유리상 고분자는 기체의 투과성은 결여되지만, 고분자쇄의 동결속박에 의한 자유부피에 따라 기체의 선택성이 높게 나타난다. 본 연구에서는 고분자로서 polyetherimide(PEI) 를 이용하여 제막조건(고분자 농도, air gap, 용매, 내부응고제 주입량 등)을 달리하는 중공사막을 제조하여, 제막변수에 따른 막의 구조 및 기체투과 특성을 검토하였다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2015.10a
• /
• pp.413-414
• /
• 2015

국내 최초로 가연성 해체폐기물 부피감용을 위해 안전하게 시설을 운영하고 있어 소각에 대한 국민인식 재고에 기여할 수 있으며, 우라늄변환시설의 가연성 해체 폐기물 소각을 통해 U 핵종오염 폐기물 소각기술을 확보하여 원자력시설 운영 효율향상, 처분비용 절감 뿐만 아니라 유해물질의 무해화로 최종처분장의 안전성 관리 최적화에 기여하고, 향후 원자력시설의 해체 및 해체 폐기물 처리/처분사업에 기술을 적극 활용할 예정이다.

• Journal of Dental Rehabilitation and Applied Science
• /
• v.37 no.3
• /
• pp.130-137
• /
• 2021

Purpose: The various suture techniques can be utilized in order to maximize the keratinized tissue healing around dental implants. The aim of this study is to compare the soft tissue healing pattern between two different suture techniques after implant placement. Materials and Methods: 15 patients with 18 implants were enrolled in this study. Simple implant placement without any additional bone graft was performed. Two different suture techniques were used to tug in the mobilized flap near the healing abutment after paramarginal flap design. Digital intraoral scan was performed at baseline, post-operation, stitch out, and 3 months after operation. The scan data were aligned using multiple points such as cusp, fossa of adjacent teeth, and/or healing abutment. After subtracting scan data at baseline with other time-point results, closed space indicating volume increment of peri-implant mucosa was selected. The volume of the close space was measured in mm³. The volume between two suture techniques at three time-points was compared using nonparametric rank-based analysis. Results: Healing was uneventful in both groups. Both suture technique groups showed increased soft tissue volume immediately after surgery. The amount of volume increment significantly decreased after 3 months (P < 0.001). Flap folding suture group showed higher median of volume increment than interrupted suture group after 3 months without any statistical significance (P > 0.05). Conclusion: After paramarginal flap reflection, the raised flaps stabilized by flap folding suture showed relatively higher volume maintenance after 3-month healing period. However, further studies are warranted.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.16 no.1
• /
• pp.93-105
• /
• 2018

In Korea, a huge amount of radioactive concrete waste will be generated through decommissioning of nuclear facilities in the near future; therefore, optimum technology for the treatment of concrete waste should be reviewed thoroughly and the future direction of technology development should be discussed. In this paper, many domestic and foreign examples of generation of radioactive concrete waste were pieced together and the characteristics of radioactive concrete waste were examined. Moreover, we reviewed trends in technology development by analyzing the examples of various studies and practical applications of treatment technologies, such as mechanical decontamination, chemical decontamination, volume reduction, recycling and solidification, and also tried to understand the limitations of existing technologies and determine a direction for technical improvement.