RISS 학술연구정보서비스

검색
다국어 입력

http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.

변환된 중국어를 복사하여 사용하시면 됩니다.

예시)
  • 中文 을 입력하시려면 zhongwen을 입력하시고 space를누르시면됩니다.
  • 北京 을 입력하시려면 beijing을 입력하시고 space를 누르시면 됩니다.
닫기
    인기검색어 순위 펼치기

    RISS 인기검색어

      검색결과 좁혀 보기

      선택해제

      오늘 본 자료

      • 오늘 본 자료가 없습니다.
      더보기
      • 무료
      • 기관 내 무료
      • 유료
      • SCIESCOPUSKCI등재

        Estimation of fuel operating ranges of fusion power plants

        Slavomir Entler,Jan Horacek,Ondrej Ficker,Karel Kovarik,Michal Kolovratnik,Vaclav Dostal Korean Nuclear Society 2023 Nuclear Engineering and Technology Vol.55 No.7

        The fuel operating ranges of fusion tokamak-based power plants are estimated using the improved engineering breakeven equation. The Lawson criterion equations are derived in the form of a triple product with a focus on engineering breakeven and the subbreakeven operating range. The relationship of fuel parameters to the power plant net efficiency is outlined. Analysis shows that the operating ranges of the suitable fuel parameters form a closed area, the size of which affects the net efficiency of the power plant. The obtained fuel operating ranges confirm the well-known fact that DT fuel is currently the only fusion fuel useable in tokamak-based fusion power plants. It is also shown that the energy utilization of pB fuel is possible in the subbreakeven operating range but is conditioned by the very high efficiency of the power plant equipment. For the utilization of DD, DHe3, and pB fuels, the required magnetic fields are indicatively estimated.

      • KCI등재

        High heat flux limits of the fusion reactor water-cooled first wall

        Pavel Zacha,Slavomir Entler 한국원자력학회 2019 Nuclear Engineering and Technology Vol.51 No.5

        The water-cooled WCLL blanket is one of the possible candidates for the blanket of the fusion powerreactors. The plasma-facing first wall manufactured from the reduced-activation ferritic-martensitic steelEurofer97 will be cooled with water at a typical pressurized water reactor (PWR) conditions. Accordingto new estimates, the first wall will be exposed to peak heat fluxes up to 7 MW/m2 while the maximumoperated temperature of Eurofer97 is set to 550 C. The performed analysis shows the capability of thedesigned flat first wall concept to remove heat flux without exceeding the maximum Eurofer97 operatingtemperature only up to 0.75 MW/m2. Several heat transfer enhancement methods (turbulatorpromoters), structural modifications, and variations of parameters were analysed. The effects of particularmodifications on the wall temperature were evaluated using thermo-hydraulic three-dimensionalnumerical simulation. The analysis shows the negligible effect of the turbulators. By the combination ofthe proposed modifications, the permitted heat flux was increased up to 1.69 MW/m2 only. The resultsindicate the necessity of the re-evaluation of the existing first wall concepts.

      연관 검색어 추천

      이 검색어로 많이 본 자료

      활용도 높은 자료

      해외이동버튼