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The Formulation and Application of the Transfer-Scattering Matrix Method to Space-, Energy-, and Angular-Dependent Fast Reactor Kinetics

H. L. Dodds, Jr., J. C. Robinson, A. R. Buhl

Nuclear Science and Engineering / Volume 47 / Number 3 / March 1972 / Pages 262-274

Technical Paper / dx.doi.org/10.13182/NSE72-A22413

A transfer and scattering matrix technique is used to solve one-dimensional, time-dependent, multigroup, discrete ordinates equations and those including the delayed-neutron equations. The solution is obtained in the frequency domain as a distributed parameter transfer function. This technique can accomodate anisotropic, spatially distributed extraneous sources and general anisotropic scattering. The numerical problems associated with the technique are analyzed, and a procedure is presented for controlling them. The results obtained with this technique are in good agreement with (a) statics results obtained from standard discrete ordinates calculations, and (b) experimental kinetics noise data obtained from a critical fast assembly. Calculated results of a simulated pulsed-neutron experiment on a subcritical fast assembly are presented.