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Spent fuel transfer project completed at INL
Work crews at Idaho National Laboratory have transferred 40 spent nuclear fuel canisters into long-term storage vaults, the Department of Energy’s Office of Environmental Management has reported.
A. L. Wight, K. F. Hansen, D. R. Ferguson
Nuclear Science and Engineering | Volume 44 | Number 2 | May 1971 | Pages 239-251
Technical Paper | doi.org/10.13182/NSE71-A19671
Articles are hosted by Taylor and Francis Online.
An approximate solution-of the multigroup neutron diffusion kinetics equations with delayed neutrons in two-dimensional geometry can be obtained by matrix splitting methods based on an Alternating-Direction Implicit (ADI) scheme. The method is shown to be consistent and numerically stable. An exponential transformation of the semi-discrete equations reduces the truncation error so that the method becomes usable for practical computations. The results of numerical experiments are presented to illustrate the accuracy and stability of the method. These results indicate that another splitting method based on an Alternating-Direction Explicit scheme is slightly superior.