ITER test-blanket safety assessment

被引:2
作者
Bartels, HW
Enoeda, M
Fütterer, M
Kleefeldt, K
McCarthy, K
机构
[1] JWS, ITER Garching, D-85748 Garching, Germany
[2] Japan Atom Energy Res Inst, Blanket Engn Lab, Naka, Ibaraki 3110193, Japan
[3] CEA Cadarache, DRN, DER, SPRC, F-13108 St Paul Durance, France
[4] Forschungszentrum Karlsruhe, IRS, D-76021 Karlsruhe, Germany
[5] INEEL, Idaho Falls, ID 83415 USA
关键词
assessment; ITER; safety blanket;
D O I
10.1016/S0920-3796(00)00565-2
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
One of the missions of the International Thermonuclear Experimental Reactor (ITER) project is to serve as a test bed for various test blanket concepts. Part of the design for these test modules is to assess their impact on the safety of ITER. This paper presents a set of safety analyses, which were performed on a consistent basis of analysis assumptions and safety requirements. The four basic concepts investigated are a helium-cooled ceramic breeder, a water-cooled ceramic breeder, a water-cooled Pb-17Li breeder, and a liquid lithium self-cooled concept. The analysis performed so far has confirmed the expectation of little safety impact from the test modules, except in a few areas. The use of liquid lithium poses well-known risks of chemical reactivity, which need to be further addressed. For the water-cooled Pb-17Li concept the need was confirmed for further R&D on reactivity of Pb-17Li with water to quantitatively assess bounding scenarios. For the water-cooled ceramic test module the analysis has identified the issue of excessive Be-steam reactions, which needs further investigations. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:331 / 336
页数:6
相关论文
共 3 条
  • [1] Boccaccini LV, 1999, FZKA6127
  • [2] *ITER FIN DES REP, 1999, ITER EDA DOC SER, V14
  • [3] JONGEWARD K, 1998, UPDATED BREEDER BLAN