OVERVIEW OF FUSION BLANKET R&D IN THE US OVERTHE LAST DECADE

M. A. ABDOU; N. B. MORLEY; A. Y. YING; S. SMOLENTSEV; P. CALDERONI

추천

검색

자료유형: 학술저널

저자정보: M. A. ABDOU N. B. MORLEY A. Y. YING S. SMOLENTSEV P. CALDERONI

저널정보: 한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology 제37권 제5호

발행연도: 2005.1

수록면: 401 - 422 (22page)

이용수

📌

연구주제

📖

연구배경

🔬

연구방법

🏆

연구결과

초록· 키워드

오류제보하기

We review here research and development progress achieved in US Plasma Chamber technology roughly over the last decade. In particular, we focus on two major programs carried out in the US: the APEX project (1998-2003) and the US ITER TBM activities (2003-present). The APEX project grew out of the US fusion program emphasis in the late 1990s on more fundamental science and innovation. APEX was commissioned to investigate novel technology concepts for achieving high power density and high temperature reactor coolants. In particular, the idea of liquid walls and the related research is described here, with some detailed examples of liquid metal and molten salt magnetohydrodynamic and free surface effects on flow control and heat transfer. The ongoing US ITER Test Blanket Module (TBM) program is also described, where the current first wall / blanket concepts being considered are the dual coolant lead lithium concept and the solid breeder helium cooled concepts, both using ferritic steel structures. The research described for these concepts includes both thermofluid MHD issues for the liquid metal coolant in the DCLL, and thermomechanical issues for ceramic breeder packed pebble beds in the solid breeder concept. Finally, future directions for ongoing research in these areas are described

#Liquid Walls #Magnetohydrodynamics #Free Surface Flow #Packed Bed Thermomechanics #APEX #ITER Test Blanket Modules

참고문헌 (33)

참고문헌 신청

/ 1951 / ？Significance of liquid-film coefficientsin gas absorption : 1460 ~ 1467

/ 1986 / ？Deuterium-Tritium Fuel Self-Sufficiency in FusionReactors？ : 250 ~ 285

/ 1986 / ？Uncertainties in Predictionof Tritium Breeding in Candidate Blanket Designs Due toPresent Uncertainties in Nuclear Data Base : 286 ~ 306

/ 1995 / ？A Volumetric Neutron Source for FusionNuclear Technology Testing and Development 27 : 111 ~ 153

/ 1998 / ？Overview of ARIES-RS tokamak fusion power plant 41 : 365 ~ 370

함께 읽어보면 좋을 논문

논문 유사도에 따라 DBpia 가 추천하는 논문입니다. 함께 보면 좋을 연관 논문을 확인해보세요!