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D. R. Harris, J. A. Mitchell
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 221-238
Technical Paper | doi.org/10.13182/NSE71-A19670
Articles are hosted by Taylor and Francis Online.
In the design of power reactors containing lattices of fuel rods in liquid coolant, it would be useful to employ cell-averaged transport parameters reflecting anisotropic neutron migration when this is significant. Measurements and Monte Carlo calculations of anisotropic neutron migration are described for rod lattices. The well-known flux peaking near thin sources is found to be accompanied by thin source effects on migration areas. Situations of substantial migration anisotropy and thin source effects are delimited.
