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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Dong Won Lee et al.
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 48-51
ITER | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8874
Articles are hosted by Taylor and Francis Online.
In order to verify the integrity of the first wall (FW) of the International Thermonuclear Experimental Reactor (ITER) the fabricated Be/Cu mock-ups were tested at the TSEFEY, e-beam facility, in Efremov, Russia. The Be/Cu mock-ups were joined with CuCrZr for a heat sink material among the Cu alloys and 316L austenitic stainless steel (SS316L) tubes for a coolant and then, joined with Be tiles for an armor material. Hot Isostatic Pressing (HIP) was used as a manufacturing method at 1050 °C, 100 MPa for 2 hours for a Cu/SS joining and at 620 °C, 100 MPa for 2 hours for a Be/Cu joining. The high heat flux (HHF) tests were performed for two Be/Cu mock-ups with a 2.5 MW/m2 heat flux and 80 sec durations, which were determined from a preliminary analysis with ANSYS-11. The temperature results from the test showed a good agreement with the analysis results and the fatigue lifetime was evaluated from the strain analysis results.