TY - GEN
T1 - TBR and shielding analyses in support of ST-FNSF study
AU - El-Guebaly, L.
AU - Mynsberge, L.
AU - Jaber, A.
AU - Menard, J.
AU - Brown, T.
PY - 2013
Y1 - 2013
N2 - The maximum achievable tritium breeding ratio (TBR), the dose to the insulator of the Cu coils, and the radial build definition are among numerous design issues investigated in detail for a Fusion Nuclear Science Facility (FNSF) based on the spherical tokamak (ST) concept. The ongoing PPPL study is considering a range of machine sizes with 1-2.2 m major radius. Preliminary shielding analysis for the PF coils of the intermediate size machine (R∼1.7 m) indicated excessive dose to the cyanate ester/epoxy organic insulator, suggesting a more radiation resistant ceramic insulator such as MgO. The 3-D analysis predicts a TBR of ∼1 when the details of the dual-cooled LiPb blanket and outboard penetrations are included in the model. Potential means to increase the TBR were investigated. Understanding the impact of various device sizes on the TBR is another important ongoing research activity to determine the threshold in device size for achieving T self-sufficiency.
AB - The maximum achievable tritium breeding ratio (TBR), the dose to the insulator of the Cu coils, and the radial build definition are among numerous design issues investigated in detail for a Fusion Nuclear Science Facility (FNSF) based on the spherical tokamak (ST) concept. The ongoing PPPL study is considering a range of machine sizes with 1-2.2 m major radius. Preliminary shielding analysis for the PF coils of the intermediate size machine (R∼1.7 m) indicated excessive dose to the cyanate ester/epoxy organic insulator, suggesting a more radiation resistant ceramic insulator such as MgO. The 3-D analysis predicts a TBR of ∼1 when the details of the dual-cooled LiPb blanket and outboard penetrations are included in the model. Potential means to increase the TBR were investigated. Understanding the impact of various device sizes on the TBR is another important ongoing research activity to determine the threshold in device size for achieving T self-sufficiency.
KW - fusion nuclear science facility
KW - neutron wall loading distribution
KW - radial build
KW - shielding
KW - tritium breeding ratio
UR - https://www.scopus.com/pages/publications/84890506981
UR - https://www.scopus.com/inward/citedby.url?scp=84890506981&partnerID=8YFLogxK
U2 - 10.1109/SOFE.2013.6635323
DO - 10.1109/SOFE.2013.6635323
M3 - Conference contribution
AN - SCOPUS:84890506981
SN - 9781479901715
T3 - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
BT - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
T2 - 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
Y2 - 10 June 2013 through 14 June 2013
ER -