• 제목/요약/키워드: ITER tokamak

검색결과 21건 처리시간 0.021초

Focus Wide - ITER장치의 성공저인 운전을 위한 ITPA회의 개최

  • 국가핵융합연구소
    • 핵융합뉴스레터
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    • 통권42호
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    • pp.18-19
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    • 2009
  • 국가핵융합연구소는 녹색 에너지로 기대되는 핵융합 에너지의 개발을 위해 선진 7개국이 공동으로 추진하고 있는 국제핵융합실험로(ITER)의 성공적인 운전에 관련된 현안 사안을 다루는 ITPA(International Tokamak Physics Activity) 전문가 회의를 지난 4월 21일부터 24일까지 4일간 국가핵융합연구소 회의실에서 개최하였다.

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ITER 사업의 삼중수소 연료주기 기술 (Tritium Fuel Cycle Technology of ITER Project)

  • 윤세훈;장민호;강현구;김창석;조승연;정기정;정흥석;송규민
    • 한국수소및신에너지학회논문집
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    • 제23권1호
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    • pp.56-64
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    • 2012
  • The ITER fuel cycle is designed for DT operation in equimolar ratio. It involves not only a group of fuelling system and torus cryo-pumping system of the exhaust gases through the divertor from the torus in tokamak plant, but also from the exhaust gas processing of the fusion effluent gas mixture connected to the hydrogen isotope separation in cryogenic distillation to the final safe storage & delivery of the hydrogen isotopes in tritium plant. Tritium plant system supplies deuterium and tritium from external sources and treats all tritiated fluids in ITER operation. Every operation and affairs is focused on the tritium inventory accountancy and the confinement. This paper describes the major fuel cycle processes and interfaces in the tritium plant in aspects of upcoming technologies for future hydrogen and/or hydrogen isotope utilization.

이터 초전도자석 전원공급장치 현장 설치현황 및 시운전 계획 (KO AC/DC Converter System Installation Status and Commissioning Plan at ITER Site)

  • 송인호;오종석
    • 전력전자학회논문지
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    • 제27권5호
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    • pp.397-401
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    • 2022
  • The construction of the ITER tokamak machine is ongoing at a 77% process rate to achieve the first plasma in 2025. The 18 sets of power supply systems comprising 400 MVA thyristor AC/DC converters for the superconducting magnets supplied by Korea (KO) are being installed with other systems, such as PF converters (China), DC busbars (Russia), and cooling water systems (India), in two buildings (Europe). The system interfaces have been defined during the design stage, and the systems have been manufactured. However, during the on-site installation work, several installation and integration issues emerged due to the manufacturing tolerance and design mistakes. To continue the installation and testing, the engineers of each system resolved the interface issues, planned the commissioning, and integrated the test plan. This paper describes the on-site installation status and issues and the commissioning plan of KO AC/DC converters.

Characteristics of Transmutation Reactor Based on LAR Tokamak

  • Hong, B.G.
    • 한국진공학회:학술대회논문집
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    • 한국진공학회 2012년도 제43회 하계 정기 학술대회 초록집
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    • pp.431-431
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    • 2012
  • A compact tokamak reactor concept as a 14 MeV neutron source is desirable from an economic viewpoint for a fusion-driven transmutation reactor. LAR (Low Aspect Ratio) tokamak allows a potential of high "see full txt" operation with high bootstrap current fractions and can be used for a compact fusion neutron source. For the optimal design of a reactor, a radial build of reactor components has to be determined by considering the plasma physics and engineering constraints which inter-relate various reactor components and are constrained to use ITER physics and technology. In a transmutation reactor, the blanket should produce enough tritium for tritium self-sufficiency and the neutron multiplication factor, keff should be less than 0.95 to maintain sub-criticality. The shield should provide sufficient protection for the superconducting toroidal field (TF) coil against radiation damage and heating effects of the fusion neutrons, fission neutrons, and secondary gammas. In this work, characteristics of transmutation reactor based on LAR tokamak is investigated by using the coupled system analysis.

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ZIF-11을 이용한 수소 동위원소 분리 (Hydrogen Isotope Separation by using Zeolitic lmidazolate Frameworks (ZIF-11))

  • 이슬지;오현철
    • 한국재료학회지
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    • 제30권12호
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    • pp.655-659
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    • 2020
  • Hydrogen isotopes (i.e. deuterium and tritium) are supplied to the tokamak in the International Thermonuclear Experimental Reactor (ITER) fuel cycle. One important part of the ITER fuel cycle is the recycling of unused fuel back to the tokamak, as almost 99 % of fuel is unburned during fusion reaction. For this, cryogenic distillation has been used in the isotope separation system (ISS) of ITER, but this technique tends to be energy-intensive and to have low selectivity (typically below 1.5 at 24 K). Recently, efficient isotope separation by porous materials has been reported in the so-called quantum sieving process. Hence, in this study, hydrogen isotope adsorption behavior is studied using chemically stable ZIF-11. At low temperature (40 K ~ 70 K), the adsorption increases and the sorption hysteresis becomes stronger as the temperature increases to 70K. Molar ratio of deuterium to hydrogen based on the isotherms shows the highest (max. 14) ratio at 50 K, confirming the possibility of use as a potential isotope separation material.

Comparisons of internal self-field magnetic flux densities between recent Nb3Sn fusion magnet CICC cable designs

  • Kwon, S.P.
    • 한국초전도ㆍ저온공학회논문지
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    • 제18권3호
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    • pp.10-20
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    • 2016
  • The Cable-In-Conduit-Conductor (CICC) for the ITER tokamak Central Solenoid (CS) has undergone design change since the first prototype conductor sample was tested in 2010. After tests showed that the performance of initial conductor samples degraded rapidly without stabilization, an alternate design with shorter sub-cable twist pitches was tested and discovered to satisfy performance requirements, namely that the minimum current sharing temperature ($T_{cs}$) remained above a given limit under DC bias. With consistent successful performance of ITER CS conductor CICC samples using the alternate design, an attempt is made here to revisit the internal electromagnetic properties of the CICC cable design to identify any correlation with conductor performance. Results of this study suggest that there may be a simple link between the $Nb_3Sn$ CICC internal self-field and its $T_{cs}$ performance. The study also suggests that an optimization process should exist that can further improve the performance of $Nb_3Sn$ based CICC.

Parametric Study for Conductor Design of KSTAR PF Coils

  • Yoon, Cheon-Seog;Qiuliang Wang;Kim, Myungkyu;Kim, Keeman;Lee, Dong-Ryul
    • Journal of Mechanical Science and Technology
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    • 제16권2호
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    • pp.227-234
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    • 2002
  • Large superconducting magnets such as ITER (International Thermonuclear Experimental Research) or KSTAR (Korean Superconducting Tokamak Advanced Research) magnet system adopted a cable-in-conduit conductor (CICC) using a forced-flow cooling system. Main optimization criteria for the conductor design of superconducting magnet system are stability margin and CICC cooling requirements. A zero-dimensional method is applied for the calculation of stability and the conductor optimization. In order to increase conductor performance, three different strands, ITER HP-I and HP-II, and KSTAR HP-Ⅲ, are tested. The strand characteristics of KSTAR HP-Ⅲ are measured in the Samsung's PPMS and Jc measurement system, and applied for this study. Also, the strand diameters, 0.81 mm and 0.78 mm are considered for this study, due to design change. Based on this result, the proposed configuration of CICC has been fabricated.

국제핵융합실험로 삼중수소 연료주기 (Tritium Fuel Cycle of the International Thermonuclear Experimental Reactor)

  • 송규민;손순환;정흥석;윤세훈;정기정
    • Korean Chemical Engineering Research
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    • 제50권4호
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    • pp.595-603
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    • 2012
  • 국제핵융합실험로(ITER)가 2019년까지 7개국의 공동개발사업으로 건설될 예정이다. ITER의 핵융합연료주기는 핵융합진공용기, 삼중수소 플랜트, 연료공급부로 구성되어 있다. 이중에서 삼중수소 플랜트는 핵융합연료주기를 위한 중 수소와 삼중수소의 저장, 공급, 분리, 제거, 회수 등의 기능을 제공한다. 삼중수소 플랜트는 외부에서 중수소와 삼중수소를 공급받아 저장 공급하는 SDS, 토카막배출처리의 TEP, 수소동위원소 분리의 ISS, 삼중수소수 및 대기 처리의 WDS ADS, 정성 정량분석의 ANS 등으로 구성된다. 이 논문에서는 삼중수소 플랜트를 구성하는 주요 공정에 대한 기능 및 설계요건을 기술하였다. 한국은 SDS 개발에 참여하고 있으며 월성원전 삼중수소 제거설비(WTRF) 건설 및 운전경험을 통해 WDS 대한 기술을 일부 확보하였다. 향후 ISS 및 TEP에 대한 기술확보를 위한 여러 분야에서의 참여 확대를 기대하고 있다.

미래 청정에너지원 KSTAR의 냉각수설비 (Cooling Water Utility of Future Clean Energy Source KSTAR)

  • 이제묘;김영진;박동성;임동석
    • 대한설비공학회:학술대회논문집
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    • 대한설비공학회 2006년도 하계학술발표대회 논문집
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    • pp.596-601
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    • 2006
  • Because of insufficiency of energy resources and pollution of environment, it is necessary to develop alternative energy sources. Nuclear fission energy is used widely for source of electric Power but being restricted due to radioactivity problem. Nuclear fission is highlighted as the new generation of nuclear energy and researched worldwide because of low risk of radiation effect. The representatives of fusion research is China's EAST, KSTAR of Korea and ITER of world. Korea Superconducting Tokamak Advanced Research(KSTAR) project is on progress for the completion in August, 2007. In this study, the research of utility system for KSTAR be carried out. The utility system of KSTAR is consist of water cooling & heating system, $N_2$ gas system, DI water system, service water system and instrument air & auto control system. The progress of KSTAR utility system is under commissioning state after construction completion. The optimal operation scenario will be verified during commissioning and adopted to the KSTAR operation.

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