Title of article :
APEX advanced ferritic steel, Flibe self-cooled first wall and blanket design
Author/Authors :
Wong، نويسنده , , C.P.C and Malang، نويسنده , , S and Sawan، نويسنده , , M and Sviatoslavsky، نويسنده , , I and Mogahed، نويسنده , , E and Smolentsev، نويسنده , , S and Majumdar، نويسنده , , S and Merrill، نويسنده , , B and Mattas، نويسنده , , R and Friend، نويسنده , , M and Bolin، نويسنده , , J and Sharafat، نويسنده , , S، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2004
Pages :
6
From page :
1599
To page :
1604
Abstract :
As an element in the US Advanced Power Extraction (APEX) program, we evaluated the design option of using advanced nanocomposite ferritic steel (AFS) as the structural material and Flibe as the tritium breeder and coolant. We selected the recirculating flow configuration as our reference design. Based on the material properties of AFS, we found that the reference design can handle a maximum surface heat flux of 1 MW/m2, and a maximum neutron wall loading of 5.4 MW/m2, with a gross thermal efficiency of 47%, while meeting all the tritium breeding and structural design requirements. This paper covers the results of the following areas of evaluation: materials selection, first wall and blanket design configuration, materials compatibility, components fabrication, neutronics analysis, thermal hydraulics analysis including MHD effects, structural analysis, molten salt and helium closed cycle power conversion system, and safety and waste disposal of the recirculating coolant design.
Journal title :
Journal of Nuclear Materials
Serial Year :
2004
Journal title :
Journal of Nuclear Materials
Record number :
1361061
Link To Document :
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