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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.
Paritosh Chaudhuri, P. Santra, S. K. S. Parashar, D. Chenna Reddy
Fusion Science and Technology | Volume 63 | Number 1 | January 2013 | Pages 59-65
Technical Note | doi.org/10.13182/FST12-489
Articles are hosted by Taylor and Francis Online.
Plasma-facing components (PFCs) are an important part of the Indian Steady State Superconducting Tokamak (SST-1) design. The main consideration in the design of PFCs is steady-state heat removal of up to 1 MW/m2 , which is nearly the limit for incident heat flux of mechanically attached graphite tiles for tokamak PFCs. SST-1 PFCs consist of divertors, passive stabilizers, baffles, and limiters and are designed for long-pulse operation, which requires active cooling of these components. During steady-state operation, the average heat loads on the divertor and passive stabilizers are expected to be 0.6 and 0.25 MW/m2 , respectively. Design considerations include two-dimensional steady-state and transient tile temperature distribution and the resulting thermal loads in PFCs during plasma operation. Thermal analysis is carried out to evaluate the thermomechanical behavior of the SST-1 PFCs. In this technical note, temperature distribution and thermally induced stresses and strains in PFCs are analyzed using a finite element method, and the effect of stress and strain on different materials used in PFCs is discussed.