TBR and shielding analyses in support of ST-FNSF study

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.

Progress in developing the STFNSF configuration

“…TBR and shielding analyses performed in support of the ST-FNSF study will be discussed in a paper by El-Guebaly [3] and details dealing with physics issues and poloidal field (PF) coil configurations to support different divertor geometries and a range of current profiles will be covered by Menard [4].…”