ARIES-RS maintenance approach for high availability

被引:23
作者
Malang, S
Najmabadi, F
Waganer, LM
Tillack, MS
机构
[1] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
[2] Univ Calif San Diego, Fus Energy Res Program, La Jolla, CA 92093 USA
[3] McDonnell Douglas Corp, St Louis, MO 63166 USA
关键词
D O I
10.1016/S0920-3796(98)00121-5
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
The ARIES-RS tokamak power plant study developed a design approach which has the potential for high availability. One of the keys for high plant availability is a design that allows rapid replacement of the power core sectors. This is achieved by using large maintenance ports for each power core sector, enabling the removal of entire sectors composed of inboard and outboard blankets, neutron shields, and upper and lower diverters. Another important feature is the location of all connections to the cooling system inside the port area and outside the plasma chamber, avoiding contamination of the chamber by coolant leaks or handling operations. Any spread of radioactive particles (e.g. tritium or dust) is avoided by the use of flasks for the transfer of used sectors to the hot cells and return of new or refurbished sectors. It is estimated that the impact on availability is less than 5% for scheduled maintenance of the power core. (C) 1998 Elsevier Science S.A. All rights reserved.
引用
收藏
页码:377 / 383
页数:7
相关论文
共 15 条
[1]  
[Anonymous], ANLFPP801
[2]  
BILLONE MC, 1997, ISFNT 4 TOK APR 6 11
[3]   IMPROVED PLASMA PERFORMANCE IN TOKAMAKS WITH NEGATIVE MAGNETIC SHEAR [J].
KESSEL, C ;
MANICKAM, J ;
REWOLDT, G ;
TANG, WM .
PHYSICAL REVIEW LETTERS, 1994, 72 (08) :1212-1215
[4]  
MAU TK, 1995, 16 EKE S FUS ENG SEP
[5]   Overview of ARIES-RS tokamak fusion power plant [J].
Najmabadi, F .
FUSION ENGINEERING AND DESIGN, 1998, 41 :365-370
[6]   THE ARIES-II AND ARIES-IV 2ND-STABILITY TOKAMAK REACTORS [J].
NAJMABADI, F ;
CONN, RW ;
BATHKE, CG ;
BAXI, CB ;
BROMBERG, L ;
BROOKS, J ;
CHENG, ET ;
DAVIS, F ;
EHST, DA ;
ELGUEBALY, LA ;
EMMERT, GA ;
DOLAN, TJ ;
HASAN, MZ ;
HASSANEIN, A ;
HERRING, JS ;
HOLMES, JA ;
HUA, T ;
HULL, A ;
JARDIN, SC ;
KESSEL, C ;
KHATER, HY ;
KRAKOWSKI, RA ;
LEUER, JA ;
LOUSTEAU, DC ;
MATTIS, R ;
MAU, TK ;
MCQUILLAN, BW ;
PICOLOGLOU, B ;
PUHN, FA ;
SANTARIUS, JF ;
SAWAN, M ;
SCHULTZ, J ;
SCHULTZ, KR ;
SHARAFAT, S ;
SNEAD, L ;
STEINER, D ;
STRICKLER, DJ ;
SVIATOSLAVSKY, IN ;
SZE, DK ;
VALENTI, M ;
WERLEY, KA ;
WONG, CPC .
FUSION TECHNOLOGY, 1992, 21 (03) :1721-1728
[7]   Improved tokamak concept focusing on easy maintenance [J].
Nishio, S ;
Ueda, S ;
Aoki, I ;
Kurihara, R ;
Kuroda, T ;
Miura, H ;
Kunugi, T ;
Seki, Y ;
Nagashima, T ;
Ohta, M ;
Adachi, J ;
Yamazak, S ;
Kawaguchi, I ;
Hashimoto, T ;
Shinya, K ;
Murakami, Y ;
Takase, H ;
Nakamura, T .
FUSION ENGINEERING AND DESIGN, 1998, 41 :357-364
[8]  
Sager P.H., 1983, ORNLFEDC822
[9]  
SHARAFAT S, 1993, 15 IEEE NPSS S FUS E
[10]   EVALUATION OF MAINTENANCE CONCEPTS SUITABLE FOR FUSION POWER-REACTORS [J].
SHERWOOD, DV ;
SEDDON, RW ;
HANCOX, R ;
SUBLET, JC .
FUSION ENGINEERING AND DESIGN, 1993, 22 (04) :367-378