The development and testing of the thermal break divertor monoblock target design delivering 20 MWm-2 heat load capability

被引:28
作者
Fursdon, M. [1 ]
Barrett, T. [1 ]
Domptail, F. [1 ]
Evans, L. I. M. [1 ]
Luzginova, N. [1 ]
Greuner, N. H. [2 ]
You, J-H [2 ]
Li, M. [2 ]
Richou, M. [3 ]
Gallay, F. [3 ]
Visca, E. [4 ]
机构
[1] CCFE, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[2] Max Planck Inst Plasma Phys, Boltzmannstr 2, D-85748 Garching, Germany
[3] CEA, IRFM, F-13108 St Paul Les Durance, France
[4] ENEA, Dept Fus & Technol Nucl Safety & Secur, I-00044 Frascati, Italy
关键词
divertor target; high heat flux; thermal break; structured interlayer; brazing; DEMO;
D O I
10.1088/1402-4896/aa8c8e
中图分类号
O4 [物理学];
学科分类号
0702 ;
摘要
The design and development of a novel plasma facing component (for fusion power plants) is described. The component uses the existing 'monoblock' construction which consists of a tungsten 'block' joined via a copper interlayer to a through CuCrZr cooling pipe. In the new concept the interlayer stiffness and conductivity properties are tuned so that stress in the principal structural element of the component (the cooling pipe) is reduced. Following initial trials with off-the-shelf materials, the concept was realized by machined features in an otherwise solid copper interlayer. The shape and distribution of the features were tuned by finite element analyses subject to ITER structural design criterion in-vessel components (SDC-IC) design rules. Proof of concept mock-ups were manufactured using a two stage brazing process verified by tomography and micrographic inspection. Full assemblies were inspected using ultrasound and thermographic (SATIR) test methods at ENEA and CEA respectively. High heat flux tests using IPP's GLADIS facility showed that 200 cycles at 20 MWm(-2) and five cycles at 25 MWm(-2) could be sustained without apparent component damage. Further testing and component development is planned.
引用
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页数:7
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