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Porous tungsten scrubbed by glow discharge cleaning
Researchers conducted experiments in Princeton Plasma Physics Laboratory’s Lithium Tokamak Experiment-Beta (LTX-β) showing glow discharge cleaning can be used to effectively clean samples of porous tungsten—used to hold liquid lithium in fusion machine inner walls—manufactured from powder-reconstituted materials, according to a paper published in Nuclear Materials and Energy.
Tungsten is widely used for plasma-facing components in fusion machines, especially in the divertor region where materials must withstand extreme levels of power flow. According to the paper, spark plasma sintering can be used to make tungsten into spongelike samples for holding liquid lithium.
Zhifang Gao, Lei Zhao, Yongdian Han
Nuclear Technology | Volume 210 | Number 3 | March 2024 | Pages 471-485
Research Article | doi.org/10.1080/00295450.2023.2229602
Articles are hosted by Taylor and Francis Online.
The residual stress of a safe-end/nozzle dissimilar metal welded joint in nuclear power plants was investigated by finite element simulation coupled with a measurement method. Cladding, butting, dissimilar metal multipass welding, machinery processes, and in-service condition were all considered to investigate the evolution of residual stress. The numerical simulation matched well with the measured values, validating the effectiveness of the numerical simulation. Tensile residual stress occurred at both inner and outer surfaces due to a double-side-welding sequence. Moreover, the highest stresses in the outer surface were located at the interface between the SA508 and clad layer due to the difference of expansion materials across the welded joint. The machinery process would greatly reduce the residual stress level and produce compressive residual stress in the base metal. When the safe end was subjected to working conditions, the tensile residual stress obviously was reduced especially on the inner surface.