• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2009년도 학술논문요약집
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• pp.53-54
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• 2009

The preliminary quantitative analysis of proliferation resistance for the five nuclear fuel cycles demonstrated that the thermal MOX fuel cycle is most vulnerable to proliferation due to the presence of pure $PuO_2$ in the fuel cycle, while the once-through fuel cycle has the highest proliferation resistance. The innovative next generation fuel cycles such as Pyro-SFR and Wet-SFR were found to have similar levels of proliferation resistance to that of the DUPIC fuel cycle which is believed to have proliferation resistance strong enough for commercial deployment. The sensitivity analysis also demonstrated the effectiveness of the proposed methodology in applying to existing and/or newly developing nuclear fuel cycles so as to improve the proliferation resistance characteristic of the fuel cycle systems.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2018년도 추계학술논문요약집
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• pp.135-136
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• 2018

• 방사성폐기물학회지
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• 제8권4호
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• pp.269-277
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• 2010

원자력의 중흥기를 맞이하여 민감한 핵연료주기 기술의 무분별한 확장을 억제하고자 다양한 핵연료주기 다자 방안이 제시되고 있다. 현재 원자력 공급국 위주의 핵연료주기 다자화가 추진되고 있는 실정에서 후행 핵연료주기 기술의 다자화 추진 추이를 파악하고자 사용후핵연료 공동 관리 시설에 대한 분석 결과를 검토하였다. 또한 후행 핵연료주기 연구개발 시설의 다자화를 제안하고 기대효과와 문제점을 검토한 후 이를 실현하기 위한 추진방안을 도출하였다.

• Korean Chemical Engineering Research
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• 제55권6호
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• pp.846-853
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• 2017

순환유동층 모사장치와 $30kW_{th}$급 파일럿 연소기를 활용하여 슬러지 순산소 유동층 연소특성을 살펴보았다. 순환유동층 모사실험에서 최소유동화속도($U_{mf}$)는 0.120 m/s로 계산되었고, 고속유동화를 위한 공탑속도는 2.5 m/s 이상으로 결정되었다. 파일럿 연소실험에서는 일반공기 및 21~40% 순산소 연소실험이 수행되었다. 배출가스 온도의 경우 21~25% 순산소 연소가 일반공기 및 30% 이상의 순산소 연소보다 상대적으로 높았다. 또한, 배출가스 중 $CO_2$ 배출농도가 21~25% 순산소 연소 범위에서 80% 이상으로 나타났다. 이를 고려한 전반적인 연소특성을 살펴 보았을 때 25% 순산소 연소가 본 슬러지 연료 연소에 대한 장시간 운전에 있어 보다 적합한 것으로 사료된다.

• 한국분무공학회지
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• 제18권4호
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• pp.182-187
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• 2013

This study was performed to investigate the effect of biodiesel derived from waste cooking oil on the spray behavior and macroscopic spray characteristics. To analyze quantitative characteristics of test fuels, injection quantity was measured at various injection pressures and the spray images of injected fuels in the pressurized chamber were obtained by using a high speed camera and image analysis system. Based on the measured spray images, the spray tip penetration and spray cone angle were investigated at various energizing timings and injection pressures. In this work, the experimental results showed that the injection quantity of waste cooking biodiesel indicated the higher quantities than diesel at high injection pressure. As the injection pressure was increased, the spray tip penetrations of biodiesel were higher value than diesel. The difference of penetration between biodiesel and conventional diesel fuel was reduced in accordance with the increase of injection pressure. Also, the spray angles of diesel were larger than that of biodiesel because diesel fuel has lower viscosity than biodiesel. In addition, the spray evolution processes of biodiesel fuel at various injection pressures and the elapsed time after the injection were compared to the conventional diesel fuel.

• 방사성폐기물학회지
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• 제20권4호
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• pp.469-488
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• 2022

Technology for high-level-waste disposal employing a multibarrier concept using engineered and natural barrier in stable bedrock at 300-1,000 m depth is being commercialized as a safe, long-term isolation method for high-level waste, including spent nuclear fuel. Managing heat generated from waste is important for improving disposal efficiency; thus, research on efficient heat management is required. In this study, thermal management methods to maximize disposal efficiency in terms of the disposal area required were developed. They efficiently use the land in an environment, such as Korea, where the land area is small and the amount of waste is large. The thermal effects of engineered barriers and natural barriers in a high-level waste disposal repository were analyzed. The research status of thermal management for the main bedrocks of the repository, such as crystalline, clay, salt, and other rocks, were reviewed. Based on a characteristics analysis of various heat management approaches, the spent nuclear fuel cooling time, buffer bentonite thermal conductivity, and disposal container size were chosen as efficient heat management methods applicable in Korea. For each method, thermal analyses of the disposal repository were performed. Based on the results, the disposal efficiency was evaluated preliminarily. Necessary future research is suggested.

• 방사성폐기물학회지
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• 제20권1호
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• pp.119-126
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• 2022

This study provides technical information about the nuclear fuel handling process, which consists of various subprocesses starting from new fuel receipt to spent fuel shipment at a nuclear power plant and the design requirements of fuel handling equipment. The fuel handling system is an integrated system of equipment, tools, and procedures that allow refueling, handling and storage of fuel assemblies, which comprise the fuel handling process. The understanding and reaffirming of detailed code requirements are requested for application to the design of the fuel handling and storage facility. We reviewed the design requirements of the fuel handling equipment for its adequate cooling, prevention of criticality, its operability and maintainability, and for the prevention of fuel damage and radiological release. Furthermore, we discussed additional technical issues related to upgrading the current code requirements based on the modification of the fuel handling equipment. The suggested information provided in this paper would be beneficial to enhance the safety and the reliability of the fuel handling equipment during the handling of new and spent fuel.

• 자원리싸이클링
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• 제18권6호
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• pp.54-59
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• 2009

RDF 생산 기술은 국내 실정에 맞는 제조 설비로 자체 생산할 수 있는 단계이지만, 사업장 가연성 폐기물에 대한 연료화 설비가 구축된 사례는 드물다. 본 연구에서는 사업장 가연성 폐기물을 대상으로 한 RPF(Refuse Plastic Fuel) 제조 공정의 고형연료 제조 가능성에 대해 검토하였다. 고형연료는 폐합성수지, 폐지 및 폐목재의 지역별 폐기물 발생비율 기준으로 제조되었으며, 제조된 RPF의 물리적 특성을 조사하였다. 대경(대구, 경북)지역을 기준으로 제조된 RPF의 발열량이 가장 높게 나타났으며, 폐지와 폐목재의 첨가량이 늘어날수록 발열량은 감소하였다.

• 방사성폐기물학회지
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• 제18권spc호
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• pp.1-19
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• 2020

Based on the current high-level radioactive waste management basic plan and the analysis results of spent nuclear fuel characteristics, such as dimensions and decay heat, an improved geological disposal concept for spent nuclear fuel from domestic nuclear power plants was proposed in this study. To this end, disposal container concepts for spent nuclear fuel from two types of reactors, pressurized water reactor (PWR) and Canada deuterium uranium (CANDU), considering the dimensions and interim storage method, were derived. In addition, considering the cooling time of the spent nuclear fuel at the time of disposal, according to the current basic plan-based scenarios, the amount of decay heat capacity for a disposal container was determined. Furthermore, improved disposal concepts for each disposal container were proposed, and analyses were conducted to determine whether the design requirements for the temperature limit were satisfied. Then, the disposal efficiencies of these disposal concepts were compared with those of the existing disposal concepts. The results indicated that the disposal area was reduced by approximately 20%, and the disposal density was increased by more than 20%.

• 방사성폐기물학회지
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• 제21권1호
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• pp.115-147
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• 2023

The Fukushima accident in 2011 revealed some major flaws in traditional nuclear fuel materials under accidental conditions. Thus, the focus of research has shifted toward "accident tolerant fuel" (ATF). The aim of this approach is to develop fuel material solutions that lead to improved reactor safety. The application of protective coatings on the surface of nuclear fuel cladding has been proposed as a near-term solution within the ATF framework. Many coating materials are being developed and evaluated. In this article, an overview of different zirconium-based alloys currently in use in the nuclear industry is provided, and their performances in normal and accidental conditions are discussed. Coating materials proposed by different institutions and organizations, their performances under different conditions simulating nuclear reactor environments are reviewed. The strengths and weaknesses of these coatings are highlighted, and the challenges addressed by different studies are summarized, providing a basis for future research. Finally, technologies and methods used to synthesize thin-film coatings are outlined.