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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.
Cheikh M'Backé Diop
Nuclear Science and Engineering | Volume 166 | Number 1 | September 2010 | Pages 82-88
Technical Note | doi.org/10.13182/NSE09-56TN
Articles are hosted by Taylor and Francis Online.
To deal with the strong attenuation of neutral particle flux in matter, like in radiation shielding studies, several techniques are used in Monte Carlo transport codes (MCNP, MCBEND, TRIPOLI, etc.) to accelerate the simulation of neutron or gamma ray transport. The exponential transform is one of the techniques that has been applied by using first- and/or second-degree analytical importance functions. The present work extends the application of this technique to an analytical toroidal form of the importance function. In this case, the sampling of the particle track length involves the solution of a fourth-degree equation. The practical usefulness of this work can be found for neutron and gamma ray transport studies related to thermonuclear fusion tokamak devices, for example.