ITER test-blanket safety assessment

Citation
Hw. Bartels et al., ITER test-blanket safety assessment, FUSION ENG, 54(3-4), 2001, pp. 331-336
Citations number
3
Categorie Soggetti
Nuclear Emgineering
Journal title
FUSION ENGINEERING AND DESIGN
ISSN journal
09203796 → ACNP
Volume
54
Issue
3-4
Year of publication
2001
Pages
331 - 336
Database
ISI
SICI code
0920-3796(2001)54:3-4<331:ITSA>2.0.ZU;2-5
Abstract
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 th e safety of ITER. This paper presents a set of safety analyses, which were performed on a consistent basis of analysis assumptions and safety requirem ents. The four basic concepts investigated are a helium-cooled ceramic bree der, a water-cooled ceramic breeder, a water-cooled Pb-17Li breeder, and a liquid lithium self-cooled concept. The analysis performed so far has confi rmed 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 chemica l reactivity, which need to be further addressed. For the water-cooled Pb-1 7Li concept the need was confirmed for further R&D on reactivity of Pb-17Li with water to quantitatively assess bounding scenarios. For the water-cool ed ceramic test module the analysis has identified the issue of excessive B e-steam reactions, which needs further investigations. (C) 2001 Elsevier Sc ience B.V. All rights reserved.