Title :
TBR and shielding analyses in support of ST-FNSF study
Author :
El-Guebaly, L. ; Mynsberge, L. ; Jaber, Ali ; Menard, J. ; Brown, Tyler
Author_Institution :
Univ. of Wisconsin-Madison, Madison, WI, USA
Abstract :
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.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor fuel; shielding; Fusion Nuclear Science Facility; TBR analysis; copper coils; cyanate ester-epoxy organic insulator; dual-cooled LiPb blanket; intermediate size machine; radial build definition; radiation resistant ceramic insulator; shielding analysis; spherical tokamak concept; tritium breeding ratio; Coils; Heating; Insulators; Materials; Neutrons; Plasmas; Solid modeling; fusion nuclear science facility; neutron wall loading distribution; radial build; shielding; tritium breeding ratio;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635323
