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Latest News
Hanford completes 20 containers of immobilized waste
The Department of Energy has announced that the Hanford Site’s Waste Treatment and Immobilization Plant (WTP) has reached a commissioning milestone, producing more than 20 stainless steel containers of immobilized low-activity radioactive waste.
B. A. Pint
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 829-833
Technical Paper | First Wall, Blanket, and Shield | doi.org/10.13182/FST07-A1594
Articles are hosted by Taylor and Francis Online.
One proposed U.S. test blanket module (TBM) for ITER uses ferritic-martensitic alloys with both eutectic Pb-Li and He coolants at ~475°C. In order for this blanket concept to operate at higher temperatures (~750°C) for a DEMO-type reactor, several Pb-Li compatibility issues need to be addressed. A SiC/SiC composite flow channel insert is proposed to reduce the steel dissolution rate (and the magnetohydrodynamic pressure drop). Prior capsule testing examined dense, high-purity SiC in Pb-Li at 800°-1200°C and found detectable levels of Si in the Pb-Li after 2,000h at 1100°C and 1,000h at 1200°C. Current capsule experiments are examining several different SiC/SiC composite materials at 1000°C. Another issue involves Pb-Li transport between the first wall and heat exchanger. Aluminide coatings on type 316 stainless steel and Al-containing alloys capable of forming an external alumina scale have been studied in capsule experiments at 700° and 800°C for 1,000h. Model aluminide coatings made by chemical vapor deposition reduced the dissolution rate for 316SS at 800°C by a factor of 50.