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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.
Takuji Oda, Yasuhisa Oya, Kenji Okuno, Satoru Tanaka
Fusion Science and Technology | Volume 54 | Number 2 | August 2008 | Pages 537-540
Technical Paper | Materials Interactions | doi.org/10.13182/FST08-A1872
Articles are hosted by Taylor and Francis Online.
A code to model permeation behavior of hydrogen isotopes through bcc Fe was developed by means of a Monte Carlo technique. This code enables correlation of atomic-scale information such as diffusion barrier or adsorption energy with macroscopic quantities such as solubility or permeability. Model parameters were derived from results of ab initio calculations in density function theory. To validate the code, both temperaturedependent permeability and pressure-dependent solubility for hydrogen were evaluated. Simulation results provided reasonable permeability and solubility compared with experimental data, and adequately showed their temperature/pressure dependence.