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핵융합로 증식 블랑켓 냉각 충돌제트의 유동 및 열전달 특성 연구
윤마루솔,최승영,문호규,안무영,조형희 대한기계학회 2024 大韓機械學會論文集B Vol.48 No.1
핵융합로 운전을 위한 삼중수소 공급의 핵심이 되는 부품인 증식 블랑켓은 플라즈마의 복사열과입자 충돌, 증식과 증배 작용으로 인한 내부 발열 등에 노출되며 높은 열부하를 받는다. 적절한 열설계를 위하여 냉각시스템에 높은 냉각성능을 갖는 충돌제트가 사용되고 있다. 본 연구에서는 해당 충돌제트 구조의 냉각 성능 분석을 위한 수치해석을 수행하였다. 수치해석에는 ANSYS Fluent 22R2를 사용하였으며, 충돌제트 노즐과 충돌면 간 간격(H / d)을 변화시켜 열전달 효율이 높은 구조를 선정하고, 제트 홀의 유량을 Re(레이놀즈 수) 5,500 ~ 87,000까지 변화시켜 Nu 변화와 압력 강하 변화를 분석하였다. 이를 바탕으로 벽면 입사 열유속에 따른 벽 평균 온도 유지를 위한 냉각 유량을 도출하고 수치해석을 통해 이를 검증하여 적절한 냉각 유량을 공급하여 벽 온도를 유지할 수 있음을 확인하였다. Breeding blanket, a crucial component breeding tritium for the operation of a nuclear fusion reactor, is exposed to high thermal loads due to radiation from plasma, particle collisions, and heat generating reaction such as multiplying and breeding. To provide appropriate thermal design, impinging jets are employed within the cooling system. In this study, a numerical analysis was conducted to assess the cooling performance of these impinging jet structures. ANSYS Fluent 22R2 was utilized for the numerical simulations. The nozzle-to-target spacing (H / d) was varied to determine an optimal structure with efficient heat transfer, and the flow rate was varied within the range of Re 5,500 to 87,000 to analyze changes in Nusselt number and pressure drop. Based on these findings, the cooling flow rate required to maintain the appropriate wall average temperature was determined, it was confirmed that supplying the adequate cooling flow rate could maintain the wall temperature.
AE기법 이용한 JLF/STS304이종재료의 최적 마찰용접조건에 관한 연구
윤한기,이진경,이상필,공유식 한국비파괴검사학회 2003 한국비파괴검사학회지 Vol.23 No.2
저방사화 페라이트강인 JLF는 핵융합로의 블랑켓과 같은 열교환기의 재료로써 유용한 재료이다. 이 재료의 광범위한 적용을 위해서는 JLF강과 다른 재료와의 접합기술의 개발이 중요하다. 최근 두 이종재료간의 접합에는 마찰용접이 많이 이용되고 있으며 본 연구에서도 JLF강과 STS304 간의 마찰용접에 의한 용접특성을 평가하였으며 특히 비파괴기법중의 하나인 음향방출 기법을 이용하여 두 이종재료간의 용접특성 및 최적의 용접조건을 평가하였다. 음향방출 파라미터중의 하나인 카운트와 사상수 등이 최적용접조건 및 용접품질을 평가하는데 유효한 파라미터들이었다. Japanese low activation ferritic steel(JLF) is a good material for the parts of heat exchanger such as blanket and diverter. At first, JLF was developed as a candidate for structural materials in nuclear fusion applications. However, the development of the jointing technique of JLF steel to other materials is important for wide applications of this material to the industry fields. Recently the jointing technologies including diffusion bonding, brazing, roll bonding, explosive bonding and hot iso-static pressing have been studied for the heterogeneous materials of JLF-1 steel(Fe-9Cr-2W-V-Ta) and stainless steel(STS304). Friction welding is one of the most popular welding methods for two different kinds of materials. In this paper, the JLF-1 steel was jointed to STS304 by friction welding method and the optimal conditions of the friction welding discussed. Acoustic emission was used as a nondestructive technique to evaluate the weld quality in processing.
K-DEMO 핵융합실증로의 증식블랑켓 방사화 특성 평가 및 붕괴열 처리 설계
김범석(Beom Seok Kim),임기학(Kihak Im),김홍택(Hong-Tack Kim),권성진(Sungjin Kwon),박종성(Jong Sung Park) 대한기계학회 2019 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.7 No.1
국내외적으로 최근 이슈가 되고 있는 에너지 문제의 궁극적인 해결책으로서 핵융합발전기술이 대두되고 있다. 현재 국내에서는 향후 추진될 상용발전설비의 건설 및 운용에 앞서, 핵융합기술과 설비의 과학적, 공학적 실증을 위한 한국형 핵융합실증로(K-DEMO) 선행개념연구가 진행되고 있다. K-DEMO에서는 연료로 사용 될 삼중수소의 증식과 연속적인 핵융합 반응을 위한 중성자 증배를 위하여 증식블랑켓이 필수적으로 적용되어야 한다. 하지만 토카막의 운용과정에서 발생되는 중성자로 인하여, 증식블랑켓은 필연적으로 방사화가 진행되고 붕괴열을 발생하게 된다. 플라즈마 운전 직후 증식블랑켓의 구성 재질인 저방사화합금 및 텅스텐에서 발생되는 붕괴열량은 수십 kW 에 달한다. 이에 본 연구에서는 중성자로 인한 증식블랑켓의 방사화 특성을 살펴보고, 이로 인한 붕괴열 특성을 평가해 보도록 한다. Fusion technology is attracting attention as the ultimate new source of energy based on the abundance of its fuels and the social and environmental acceptability. The Korean fusion demonstration tokamak reactor (K-DEMO), a facility for the demonstration of scientific and engineering feasibility, is currently in the pre-conceptual design phase. A breeding blanket, which is essential in K-DEMO tokamak, is an important mechanical and functional component for both tritium breeding and neutron multiplying. However it must be radio-activated due to the neutron irradiation, and thus accompany decay heat generation during their maintenance. A component of reduced activation ferritic martensitic (RAFM) steel layer and tungsten first wall accompanies significant decay heats by tens of kilowatts after the plasma shutdown. We evaluate their radio-activated characteristics under the fusion neutron irradiation and demonstrate that thermal managements should be taken into account in the light of heat transfer aspects of cooling.
조승연(Seungyon Cho),유인근(In-Keun Yu),손수정(Soo Jung Son) 대한기계학회 2006 대한기계학회 춘추학술대회 Vol.2006 No.6
FUSION power offers the potential of an almost limitless source of energy for future generations but it also presents some formidable scientific and engineering challenges. Korea is one of participation countries in ITER project, and study on fusion material is also one of critical issues. A number of materials are necessary to construct the fusion reactor. Especially, structural materials for plasma facing and blanket require reliable properties under severe environments. As a basis on fusion study, material R&D is considerable of interest. Construction of ITER TBM and fabrication data are on progress for next generation nuclear fusion. In this conference, the present state and future prospects for fusion material study will be introduced.
차세대 핵융합로용 SiC/SiC 복합재료의 개발 및 연구동향
윤한기(Han-Ki Yoon) 대한기계학회 2004 대한기계학회 춘추학술대회 Vol.2004 No.8
Silicon carbide (SiC) materials have been extensively studied for high temperature components in advanced energy system and advanced gas turbine, because it has excellent high temperature strength, high elastic modulus, low coefficient of thermal expansion, high heat transfer characteristics, good resistance to oxidation, and good thermal and chemical stability. So that, the present status and future prospects of silicon (SiC) continuous fiber-reinforced SiC-matrix ceramic composites (SiC/SiC composites) is reviewed from the viewpoint of material development for applications to blanket/first wall structures in fusion powder devices and other advanced nuclear systems. In this paper, the current status of SiC/SiC composite R&D for advanced fusion reactor in ITER is introduced.
구대서,김연진,정광진,윤세훈,정흥석 한국수소및신에너지학회 2016 한국수소 및 신에너지학회논문집 Vol.27 No.2
Korea has been developing nuclear fusion fuel storage and delivery system (SDS) technologies including a basic scientific study on hydrogen storage. To develop nuclear fusion technology, it is necessary to store and supply hydrogen isotopes needed for Tokamak operation. SDS is used for storing hydrogen isotopes as a metal hydride form. The rapid hydriding of tritium is very important not only for safety reasons but also for the economic design and operation of the SDS. In this study, we designed and fabricated a medium-scale getter bed of depleted uranium (DU). The hydriding of DU has been measured by varying the initial temperature (100 - 300℃) of the DU getter bed to investigate the influence of the cooling temperature. Furthermore, we analyzed the effect of a helium blanket on the hydriding performance with 0 - 12% helium content in hydrogen.
그라비어-옵셋 프린팅을 이용한 미세패턴 형성 공정 연구
김동수(Kim Dong-Soo),배성우(Bae Sungwoo),이현아(Lee Hyun-Ah),전인수(Jeon In-Soo) 대한기계학회 2013 대한기계학회 춘추학술대회 Vol.2013 No.12
The purpose of this paper was that examine the developed system of gravure-offset printing system for printed electronics. Especially, vacuum process has been used for manufacturing process as the conventional semi-conductor manufacturing process. However, it’s difficult to be applied to the continuous process and it causes very high device’s manufacturing cost with processing cost. But these systems are suitable for continuous process and reduced the manufacturing cost. But the gravure-offset printing technique have some problems such as resolution of the printed pattern and register control. So, in this paper, we addressed the developed gravure-offset printing system with applied double etching patterned roll and double core blanket roll and through the examined the printing result, we investigated the possibility of printed electronics.