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Kafe 바로가기주관연구기관 | 서울대학교 Seoul National University |
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연구책임자 | 황용석 |
참여연구자 | 김선호 |
보고서유형 | 최종보고서 |
발행국가 | 대한민국 |
언어 | 한국어 |
발행년월 | 2019-06 |
주관부처 | 과학기술정보통신부 Ministry of Science and ICT |
등록번호 | TRKO202000001309 |
DB 구축일자 | 2020-07-29 |
키워드 | 고성능 운전모드.MHD 안정성.중성입자빔 입사.플라즈마 진단.VEST.NBIadvanced operation modes.MHD Stability.NBI.Plasma diagnostics. |
1.고성능 운전 모드 이론 및 전산모사를 통한 최적의 운전 조건 도출
2.플라즈마 가열 장치 개발 및 신개념 전류 구동 연구
3.VEST장치에서의 고급 공간분포 진단계 개발 및 고성능 운전 모드 실험
(출처 : 보고서 요약서 3P)
ㅇ Purpose & Contents
In reactor-relevant condition, advanced tokamak operation with high beta, high H factor and high bootstrap fraction needs to be realized for commercial fusion reactors. In this study, high performance reactor operation consistent with alpha-dominant burning plasmas will be de
ㅇ Purpose & Contents
In reactor-relevant condition, advanced tokamak operation with high beta, high H factor and high bootstrap fraction needs to be realized for commercial fusion reactors. In this study, high performance reactor operation consistent with alpha-dominant burning plasmas will be derived by theoretical and numerical studies on turbulence, transport and MHD stability, and experimentally demonstrated in VEST(Versatile Experiment Spherical Torus). Centrally peaked pressure profiles produced by high-power pulsed NBI system will be used to simulate alpha-heated reactor-relevant fusion plasmas for the study of high performance advanced tokamak operation (βN > 5, fBS > 0.7, H98 > 1) in a stable manner. Newly developed advanced profile diagnostics with fast time response will be a key element along with powerful heating and current drive systems to be developed in this center.
1) Obtaining the optimal operation conditions for the advanced operation mode based on the theoretical analysis and simulation study
- Study on the nondiffusive turbulent transport and MHD stability in the advanced operation mode
- Obtaining the optimal operation conditions and plasma profiles in the fusion reactor relevant plasmas based on the integrated modelling and MHD stability analysis
- Study on the achievement of the advanced operation mode with the experimental results of the various tokamaks and VEST device
2) Development of plasma heating and current drive system for the advancde operation mode
- Development of pulse-mode high power NBI system for high β operation
- Study on the efficient RF current drive method using the lower hybrid fast wave branch
3) Development of high performance diagnostic devices and experimental study on the advancde operation mode in VEST device
- target plasma (80kA, 20ms, elongation>2) discharge in VEST
- Fabrication and installation of advanced CES system and fast Thomson scattering device using the burst-mode high power Nd-YAG laser
- Development of high performance operation mode with high beta and bootstrap current fraction using different heating and current drive methods
ㅇ Results
- Development of database for reactor-relevant plasma simulations
- Development of NBI and LHFW system for heating and current drive
- Achievement of high plasma current and high density plasma discharge and experimental study on advanced operation mode
ㅇ Expected Contribution
- Secure of the integrated modelling systems and professional manpower
- Application of pulse-mode high power NBI technique and noble concept of LHFW current drive to the fusion reactor operation.
- Applying the results of high performance operation mode in VEST to the KSTAR device, and then to the K-DEMO and fusion reactor design Training the high-quality human resources for the high performance fusion device operation, fusion plasma diagnostics and control
(출처 : SUMMARY 5P)
과제명(ProjectTitle) : | - |
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연구책임자(Manager) : | - |
과제기간(DetailSeriesProject) : | - |
총연구비 (DetailSeriesProject) : | - |
키워드(keyword) : | - |
과제수행기간(LeadAgency) : | - |
연구목표(Goal) : | - |
연구내용(Abstract) : | - |
기대효과(Effect) : | - |
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