L. Laguardia

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About

Dr. L. Laguardia is a leading figure in nuclear fusion materials science, specializing in plasma-facing component (PFC) diagnostics and the critical challenge of tritium retention. Their research centers on the development and application of advanced laser-based spectroscopic techniques, particularly Laser-Induced Breakdown Spectroscopy (LIBS), for in-situ analysis of reactor components. Dr. Laguardia’s most impactful contribution is the pioneering demonstration of remote LIBS for measuring deuterium—a safe proxy for radioactive tritium—retained in the FTU tokamak’s molybdenum (TZM) toroidal limiter. This work, which has garnered 40 citations, represents a major step forward in enabling real-time, non-destructive tritium inventory monitoring during machine operations, a key safety and fuel-cycle requirement for future reactors like ITER. By proving that LIBS can be performed from a distance of ~2.5 meters during short operational breaks, Dr. Laguardia has established a viable pathway for in-vessel diagnostics without compromising vacuum integrity. Their achievements provide a crucial tool for understanding fuel retention and surface erosion, directly informing the design of next-generation fusion devices.