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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.
Haihua Zhao, Vincent A. Mousseau
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 184-195
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics | doi.org/10.13182/NT13-A15766
Articles are hosted by Taylor and Francis Online.
This paper presents extended forward sensitivity analysis as a method to improve uncertainty quantification. By including the time step and potentially grid spacing as special sensitivity parameters, the forward sensitivity method is extended as one method to quantify numerical errors. Note that by integrating local truncation errors over the whole system through the forward sensitivity analysis process, the generated time step sensitivity information reflects global numerical errors. Discretization errors can be systematically compared against uncertainties due to other physical parameters. This extension makes the forward sensitivity method a much more powerful tool than other tools of its type to help uncertainty quantification. When the relative sensitivity of the time step to other physical parameters is known, the simulation is allowed to run at optimized time steps without affecting the confidence of the physical parameter sensitivity results. The time step forward sensitivity analysis method can also replace traditional time step convergence studies that are a key part of code verification, with much less computational cost. Two well-defined benchmark problems with manufactured solutions are utilized to demonstrate the method.