11. CFETR divertor development
Explorehigh heat load handling configuration together with Remote Handling (RH) andhybrid blanket design.
Developinghigh heat load handling technology.
Integratedtesting with 10-20 MW/m2 CW heat load.
Systemdescription and main technical parameters:
CFETR divertor accommodatedwith long leg geometric configuration can realize basic functions of exhaustinghigh heat loads as well as of particles pumping and controlling.
The unique feature of CFETRdivertor design are the high heat load handling technology, to increase the TBRby using the bottom space of divertor as part of blanket, and RH compatibilityunder a complex in-vessel environment, such as strong neutron yield, high heatload and strong electromagnetic field and force during disruption.
Based on the engineeringdesign, analysis and optimization, the preliminary structure of CFETR diverteris nearly determined, as shown in Fig.1. 80 divertor modules are expected to beinstalled mainly comprising targets components and a cassette body. Advancedmaterial such as potassium tungsten, ODS-Cu and RAFM steel is planning to beused and the connecting technology is developing. The divertor will bothconsider design scheme of flat tile and monoblock as the basic units fortarget. Two RH schemes are proposed. The first scheme is referenced from theITER-like structure, which must handle a single complete divertor module. Thesecond scheme can handle the separate targets component, according to the realdamage degree of outer target, inner target, and dome target.
The new concept with hybridblanket design can be realized by removing the cassette body and select thesecond RH schemes, as shown in Fig.2 .
Through the development ofsmall, medium-sized test modules and prototype fabrication, integrated testingwith 10-20MW/m2 CW heat load, the divertor design for fusion reactorwill be finalized.
The technicalparameters are as follows:
Heatload capacity in striking area beyond 20 MW/m2 in steady state and 30MW/m2 in transient state.
Heatload capacity in non-striking area beyond 10 MW/m2 in steady stateand 20 MW/m2 in transient state.
Profileerror of plasma facing surface is less than 1 mm.
Materialconnection technology for fusion reactor materials.
IndependentRH dismounting technology for targets components.
Highheat load handling technologies