A SELF-COOLED LIQUID-METAL BLANKET FOR A TOKAMAK REACTOR

被引:1
作者
MADARAME, H
机构
[1] Nuclear Engineering Research Laboratory, Ibaraki, 319-11, Tokai-mura
关键词
D O I
10.1016/0920-3796(92)90059-D
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
A liquid metal-cooled inboard blanket for a tokamak reactor was designed to reduce the MHD pressure drop. No structure is directly connected to the first and second wall, so the currents induced in the first wall cooling channel return through distant sections of the blanket. The circuit resistance is very high because the current paths are long and produce a low pressure drop despite the fairly high coolant velocity. The total pressure drop through the blanket is estimated at less than 1 MPa and the heat transfer coefficient on the first wall is above 33 kW/m2K. The high cooling capability of the first wall is achieved without an excessive MHD pressure drop.
引用
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页码:1 / 10
页数:10
相关论文
共 7 条
[1]
THEORETICAL-STUDY OF EFFECTS OF WALL CONDUCTIVITY, NONUNIFORM MAGNETIC-FIELDS AND VARIABLE-AREA DUCTS ON LIQUID-METAL FLOWS AT HIGH HARTMANN NUMBER [J].
HOLROYD, RJ ;
WALKER, JS .
JOURNAL OF FLUID MECHANICS, 1978, 84 (FEB) :471-495
[2]
DEVELOPMENT OF A COMPUTATIONAL METHOD FOR THE FULL SOLUTION OF MHD FLOW IN FUSION BLANKETS [J].
KIM, CN ;
HADID, AH ;
ABDOU, MA .
FUSION ENGINEERING AND DESIGN, 1989, 8 :265-270
[3]
MADARAME H, 1989, FUSION ENG DES, V7, P417
[4]
COMPUTER CODE FOR ANALYZING LIQUID-METAL MHD FLOW IN RECTANGULAR DUCT UNDER STRONG TRANSVERSE MAGNETIC-FIELD [J].
MADARAME, H ;
HAGIWARA, T .
FUSION ENGINEERING AND DESIGN, 1989, 8 :167-171
[5]
ANALYSIS OF LIQUID-METAL MHD FLOW USING AN ITERATIVE METHOD TO SOLVE THE CORE FLOW EQUATIONS [J].
MCCARTHY, KA ;
TILLACK, MS ;
ABDOU, MA .
FUSION ENGINEERING AND DESIGN, 1989, 8 :257-264
[6]
SMITH DL, 1984, ANLFPP841 FIN REP