This paper focuses on a few recent advances and research developments concerning fusion radioactive waste management studies. In particular: the role of fusion power in the frame of the future production of nuclear radioactive waste, in terms of potential waste avoidance using a precautionary fusion waste management policy, activation of W and its alloys (examining and comparing the activation of W-based components in ITER, PPCS, and ARIES designs), development of a management strategy for activated materials from complex components (such as blanket and divertor), waste decay heat and maintenance questions, materials detritiation, and public acceptance of clearable and recyclable materials.
ASJC Scopus subject areas
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering