Safety assessment of two advanced ferritic steel molten salt blanket design concepts

Preliminary tritium safety analysis on China DFLL-TBM for ITER

“…An alumina coating is being advised for blanket and all ancillary system pipes to reduce tritium permeation. Corresponding data for tritium in LiPb and in structure materials are listed in Table 2 [15][16][17]. The tritium extrapolated values for the diffusivity in the steel are defined using the classical diffusion theory: D i /D j = (m j /m i ) 1/2 , where i and j are two hydrogen isotopes.…”

Safety Assessment of the ARIES Compact Stellarator Design

“…Figure 27 confirms that the magnet Nb 3 Sn superconductor cannot be cleared because of 94 Nb from Nb! and the magnet polyimide insulator cannot be cleared because of 14 C~from N!. The remaining magnet constituents can be cleared, however, within 20 to 300 yr.…”

Status of Safety and Environmental Activities in the U.S. Fusion Program

“…Both designs used ferritic steel as the structural material. 5 The results for loss of coolant accidents showed that the peak blanket temperatures remained below values where structural integrity would be lost, provided that natural convection in the vacuum vessel cooling system was initiated. An interesting result was that the Flinabe liquid wall design experienced high temperatures in a loss of flow scenario; because of the decay of Na-22 and Na-24 within the coolant itself.…”