BCTF: A High-Field Non-Nuclear User Facility for Blanket Component Testing*

The preconceptual design for a non-nuclear, high-field blanket component test facility (BCTF) is presented, with the primary mission of characterizing component operation in prototypic thermal, hydraulic, and magnetic environments. The fusion blanket, a critical part of D-T fusion concepts, is currently at a low technology readiness level and will have to be demonstrated via integrated, multi-effect tests in order to verify performance. BCTF requirements have been developed with community input and include (i) magnetic field up to 10T, similar to the inboard region of toroidal device, (ii) large experimental volume of 0.75m³, (iii) liquid metal breeder loops at relevant temperatures (300-700 C), (iv) surface (~MW/m²) and simulated volumetric heating (~MW/m³), and (v) auxiliary coolant and heat rejection loops (e.g. 8 MPa helium). These requirements produce the relevant non-nuclear environment for qualifying meter-scale blanket components at the appropriate electromagnetic, thermal, and mechanical loading, as well as high MHD Hartmann, Reynolds and interaction parameter values for liquid metal breeding blanket concepts (Li, PbLi). The BCTF design incorporates significant onsite materials, infrastructure and capability developed during fabrication of the ITER central solenoid (CS): excess Nb₃Sn CS conductor in spools and wrapped as a six-layer hexapancake, a supercritical helium cryoplant, and high-current power supplies are present and integrated into the facility design.