TY - JOUR
T1 - Pre-conceptual design and proof of principle assessments of self-cooled Toroidally symmetric lead-lithium (TSLL) blanket
AU - Smolentsev, Sergey
AU - Aduloju, Sunday
AU - Bae, Jin Whan
AU - Fan, Yuqiao
AU - Humrickhouse, Paul
N1 - Publisher Copyright:
© 2024
PY - 2024/10
Y1 - 2024/10
N2 - A new self-cooled liquid metal blanket concept called TSLL (Toroidally Symmetric Lead-Lithium) blanket is proposed and assessed, including analysis for magnetohydrodynamic (MHD) flows, structural analysis, and heat transfer and neutronics assessments using the ARC reactor with demountable magnets designed by the Commonwealth Fusion Systems (CFS) as a testbed. The proposed blanket utilizes lead-lithium (PbLi) alloy as breeder/coolant and reduced activation ferritic/martensitic (RAFM) steel as structural material. A special feature of the new concept is the toroidally symmetric flow in the blanket integrated first wall and the breeding zone to reduce the MHD pressure drop, while using anchor links to strengthen the first wall construction. Provided analysis suggests acceptable MHD pressure drop, required mechanical integrity and high tritium breeding ratio of ∼ 1.64. As a result of these assessments, the new blanket concept can be recommended for more detailed studies as a promising blanket candidate for implementation in future fusion devices.
AB - A new self-cooled liquid metal blanket concept called TSLL (Toroidally Symmetric Lead-Lithium) blanket is proposed and assessed, including analysis for magnetohydrodynamic (MHD) flows, structural analysis, and heat transfer and neutronics assessments using the ARC reactor with demountable magnets designed by the Commonwealth Fusion Systems (CFS) as a testbed. The proposed blanket utilizes lead-lithium (PbLi) alloy as breeder/coolant and reduced activation ferritic/martensitic (RAFM) steel as structural material. A special feature of the new concept is the toroidally symmetric flow in the blanket integrated first wall and the breeding zone to reduce the MHD pressure drop, while using anchor links to strengthen the first wall construction. Provided analysis suggests acceptable MHD pressure drop, required mechanical integrity and high tritium breeding ratio of ∼ 1.64. As a result of these assessments, the new blanket concept can be recommended for more detailed studies as a promising blanket candidate for implementation in future fusion devices.
KW - Anchor links
KW - MHD pressure drop
KW - Self-cooled blanket
KW - Toroidally symmetric MHD flow
KW - Tritium breeding ratio
UR - http://www.scopus.com/inward/record.url?scp=85200822288&partnerID=8YFLogxK
U2 - 10.1016/j.fusengdes.2024.114617
DO - 10.1016/j.fusengdes.2024.114617
M3 - Article
AN - SCOPUS:85200822288
SN - 0920-3796
VL - 207
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 114617
ER -