FUSION-REACTOR DESIGN STUDIES

被引:1
作者
SEKI, Y
机构
[1] Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, 311-01 Ibaraki-ken, 801-1 Naka-machi, Naka-gun
关键词
D O I
10.1016/0920-3796(94)90049-3
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
This paper is a summary of fusion reactor design studies presented and discussed at the IAEA Technical Committee Meeting and Workshop on Fusion Reactor Design and Technology, held in September 1993 at the University of California, Los Angeles. This summary does not represent all the reactor design studies carried out in the world since the last meeting in Yalta in 1986. The reactor designs presented are mostly D-T fuel cycle with both magnetic confinement and inertial confinement. As a D-He-3, only the ARIES-III was presented. Steady state and pulsed tokamak studies, stellarator and reversed field pinch reactor studies are summarized. Six recent D-T inertial confinement fusion reactors presented at the meeting are summarized. A short summary on D-He-3 reactors and fusion-fission hybrid reactor design's is given.
引用
收藏
页码:5 / 13
页数:9
相关论文
共 24 条
[1]   FUSION-REACTOR DESIGN-IV - REPORT ON THE 4TH IAEA TECHNICAL COMMITTEE MEETING AND WORKSHOP, YALTA, USSR, 26 MAY - 6 JUNE 1986 [J].
ABDOU, MA ;
BERTOLINI, E ;
HANCOX, R ;
HOGAN, WJ ;
KOSTENKO, AI ;
KULCINSKI, GL ;
MILLER, RL ;
ORLOV, VV ;
RAU, F ;
SVIATOSLAVSKY, IN ;
KUPITZ, J .
NUCLEAR FUSION, 1986, 26 (10) :1377-1428
[2]   UNITED-STATES HEAVY-ION FUSION SYSTEMS ASSESSMENT PROJECT OVERVIEW [J].
DUDZIAK, DJ ;
SAYLOR, WW ;
HERRMANNSFELDT, WB .
FUSION TECHNOLOGY, 1988, 13 (02) :207-216
[3]  
ELGUEBALY LA, 1993, 2ND P WISC S HEL 3
[4]  
GRIEGER G, 1993, SEP P TECHN COMM M W
[5]  
HUANG JH, 1993, SEP P TECHN COMM M W
[6]  
INOUE N, 1992, 14TH P INT C PLASM P
[7]  
KONDO S, 1989, FUSION ENG DES, V9, P359
[8]  
LYON JF, 1993, SEP P TECHN COMM M W
[9]  
MEIER WR, 1992, DOEER541001 REP
[10]  
MIMA K, COMMUNICATION