Home / Store / Journals / Electronic Articles / Fusion Science and Technology / Volume 47 / Number 3 / Pages 502-509
C. P. C. Wong et al.
Fusion Science and Technology / Volume 47 / Number 3 / Pages 502-509
Format:electronic copy (download)
As candidate blanket concepts for a U.S. advanced reactor power plant design, with consideration of the time frame for ITER development, we assessed first wall and blanket design concepts based on the use of reduced activation ferritic steel as structural material and liquid breeder as the coolant and tritium breeder. The liquid breeder choice includes the conventional molten salt Li2BeF4 and the low melting point molten salts such as LiBeF3 and LiNaBeF4 (FLiNaBe). Both self-cooled and dual coolant molten salt options were evaluated. We have also included the dual coolant leadeutectic Pb-17Li design in our assessment. We take advantage of the molten salt low electrical and thermal conductivity to minimize impacts from the MHD effect and the heat losses from the breeder to the actively cooled steel structure. For the Pb-17Li breeder we employ flow channel inserts of SiCf/SiC composite with low electrical and thermal conductivity to perform respective insulation functions. We performed preliminary assessments of these design options in the areas of neutronics, thermal-hydraulics, safety, and power conversion system. Status of the R&D items of selected high performance blanket concepts is reported. Results from this study will form the technical basis for the formulation of the U.S. ITER test module program and corresponding test plan.
Customers who purchased this article also purchased the following:
Your cart is empty.
Home|Invoice Payment|Nuclear Links