Abstract
Research on JApanâ€s DEMOnstration fusion reactor (JA DEMO) has focused on the radwaste management of radioactivated in-vessel components (IVCs) generated during a periodic replacement and studies on the volume reduction of these radioactivated IVCs. It is considered important to establish a maintenance management scenario and a volume reduction method for the radioactivated IVCs from the viewpoint of improving the social acceptability of JA DEMO. It was found that even a blanket first wall, which is at the highest radioactivity level, can be disposed of in a concrete pit near the land surface. On the other hand, the maintenance management such as the storage and dismantling of the IVCs in a hot cell takes into account a periodic replacement cycle and the nuclear characteristics of the IVCs. Furthermore, in order to reduce the radioactivated IVCs, a strategy for reuse and recycling has been analyzed and the R&D items were defined for JA DEMO.
Original language | English |
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Title of host publication | Fusion Energy Technology R and D Priorities |
Publisher | Elsevier |
Pages | 329-332 |
Number of pages | 4 |
ISBN (Electronic) | 9780443136290 |
ISBN (Print) | 9780443136306 |
DOIs | |
Publication status | Published - 2024 Jan 1 |
Keywords
- Beryllide
- F82H
- Hot cell
- JA DEMO
- LiTiO
- Periodic replacement
- Radwaste management
- Recycling
- Reuse
- Tritium breeding blanket