Management strategies to reduce the radioactive waste amount in fusion
The feasibility of remote handling, and hands on, recycling is assessed from limits on surface dose rates of the waste after 50 years storage at the plant site. Similarly, clearance feasibility is assessed from the residual radioactivity (energy of gamma and beta emissions, allowable limits of intake by inhalation and ingestion). Two power reactor designs, SEAFP plant model 1 and 2 are analyzed. The presence of tritium in the irradiated material is also taken into account. Large amounts of in-vessel materials can be recycled. Similarly, most of the waste arising from out-of-vessel materials can be cleared.
Bibliographic Reference: Paper presented: IAEA Technical Committee Meeting on Development in Fusion Safety, Naka (JP), October 21-25, 1996
Availability: Available from (1) as paper EN 40197 ORA
Record Number: 199710506 / Last updated on: 1997-05-09
Original language: en
Available languages: en