This arXiv preprint (not yet peer-reviewed) proposes using 14 MeV D-T fusion neutrons to irradiate feedstocks like enriched 148Nd, yielding high-specific-activity beta emitters such as 147Pm at rates exceeding one ton per gigawatt-thermal-year—roughly one billion curies annually. The authors ran OpenMC neutron-transport simulations of a tokamak blanket designed for tritium self-sufficiency, showing simultaneous radioisotope breeding and fuel-cycle closure. Unlike current reactor-based production limited to grams or kilograms, this route could scale dramatically once commercial fusion plants exist. The work overlooks near-term regulatory and economic barriers: licensing multi-ton quantities of high-activity material would face strict NRC and IAEA scrutiny, and the assumed 2035+ fusion timeline clashes with slower ITER and private-sector roadmaps. It also underplays waste streams from activated structural materials. Cross-referencing with a 2024 Nuclear Technology review on radioisotope power systems and a 2023 Fusion Engineering & Design paper on tritium-breeding blankets reveals synergies the preprint misses—namely, that 147Pm and 63Ni outputs could directly power off-grid sensors or lunar bases where solar and chemical batteries fail over decades. Computational methodology here relies on idealized neutron spectra without experimental validation or uncertainty quantification from real tokamak data, limiting predictive power until integrated test facilities exist.