STRUCTURAL DESIGN CRITERIA DEVELOPMENT NEEDS FOR A EUROPEAN DEMO

被引:12
|
作者
Porton, M. [1 ]
Aktaa, J. [2 ]
Bachmann, C. [3 ]
Fernandez, P. [4 ]
Kalsey, M. [1 ]
Lebarbe, T. [5 ]
Petesch, C. [5 ]
Timmis, W. [1 ]
机构
[1] Culham Sci Ctr, EURATOM CCFE, Abingdon, Oxon, England
[2] Karlsruhe Inst Technol, Inst Appl Mat, Assoc KIT Euratom, D-76344 Eggenstein Leopoldshafen, Germany
[3] EFDA, D-85748 Garching, Germany
[4] Natl Fus Lab, Div Technol, CIEMAT, Madrid 28040, Spain
[5] CEA Saclay DEN, LISN, DM2S, SEMT, F-91191 Gif Sur Yvette, France
基金
英国工程与自然科学研究理事会;
关键词
design criteria; DEMO; structural integrity; COOLED DIVERTOR; COMPONENTS; ITER; QUALIFICATION; BEHAVIOR; HELIUM;
D O I
10.13182/FST14-781
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 verification of the structural components of demonstration fusion power plants requires design criteria developed specifically for those components and the unique conditions at which they are operated. Therefore the creation of a body of structural design criteria appropriate for demonstration fusion power plants is an important activity, with particular attention required for the in-vessel components of the divertor and blanket. For posited failure modes associated with the candidate in-vessel components for the current European Demonstration Power Plant design (EU DEMO), this paper highlights the gaps identified in the leading suites of relevant structural design criteria (ASME BPVC Division HI, AFCEN RCC-MRx, ITER SDC-IC). Opportunities for innovative development are then explored for these gaps. Finally, a development path for structural design criteria against the needs of EU DEMO is discussed.
引用
收藏
页码:18 / 27
页数:10
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