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텅스텐 모노블락을 적용한 한국형 핵융합 실증로 디버터의 열수력적 최적 설계
권성진(Sungjin Kwon),임기학(Kihak Im),박종성(Jong Sung Park) 대한기계학회 2017 대한기계학회 춘추학술대회 Vol.2017 No.11
A conceptual design study of the Korean fusion demonstration reactor (K-DEMO) has been carried out since 2012 as following the Korean fusion development roadmap based on the Fusion Energy Development Promotion Law (FEDPL) legislated in 2007. The present in-vessel components of the K-DEMO have been studied for the 2,200 MW of fusion power. Almost half of the plasma power should be cooled down in the divertor. Especially, 10 MW/m² of the peak heat flux locally concentrates on the narrow section of the divertor target. To faithfully cool down the heat load, the selection of materials that the divertor is important as well as the decision of design parameters. Especially, the choice and design of the heat sink material in the divertor target are quite significant because the heat sink directly interfaced with the coolant. Reduced activation ferritic martensitic (RAFM) steel and CuCrZr have been considered the most promising candidates as the heat sink material. The preliminary designs of the high heat flux (HHF) units operating within materials’ own allowable temperature were derived by accomplishing thermohydraulic analyses for RAFM and CuCrZr. Based on the designs of HHF units with a support structure.
K-DEMO 핵융합실증로의 에너지원항: 중수소-삼중수소 반응에 따른 블랑켓 및 디버터 구조물의 붕괴열과 비방사능 평가
김범석(Beom Seok Kim),임기학(Kihak Im),김홍택(Hong-tack Kim),권성진(Sungjin Kwon),홍석호(Suk-ho Hong) 대한기계학회 2019 대한기계학회 춘추학술대회 Vol.2019 No.11
In the preliminary research phase, we quantify potential energy from the activation of major in-vessel components such as breeding blanket and divertor due to neutron generation during a D-T fusion reaction in K-DEMO. After two years of full fusion operation of K-DEMO, the decay heat which readily provokes potential behavior of hazardous inventories is estimated as 55.6 ㎿ and 8.40 ㎿ from activated blankets and divertors, respectively. Particularly tungsten first wall of an equatorial blanket shows a considerable amount of decay heat of 149 W/㎏, while it is about 92.3 W/㎏ for a structural material of reduced activation ferritic martensitic (RAFM) steel. Local specific radioactivity in the blanket reaches 2.42×1015 Bq/㎏, and 2.39×1014 Bq/㎏ for W first wall and RAFM steel structures, respectively. We will demonstrate the cooling temperature as a function of decay time is an important factor to assess thermal behavior of breeding blanket and divertor, and it should be implemented into safety system to secure the components as intact as possible against thermal failure. We will show that all in-vessel components can be managed within low level limits on their activation in accordance with regulatory guidelines for nuclear safety concerns. The results of this study will be implemented in a pre-conceptual design of K-DEMO and will contribute to the establishment of a regulatory framework.
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.