GENERATION OF TIME-DEPENDENT NEUTRON-TRANSPORT SOLUTIONS IN INFINITE MEDIA
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The multiple collision technique as applied to the monoenergetic time-dependent neutron transport equation for pulsed plan source emission in an infinite medium is used to obtain the flux due to a pulsed point source in the same medium. This result is then integrated to determine the flux due to the corresponding pulsed line source problem. The semi-infinite albedo problem is also shown to be solvable using the multiple collision approach. A generalization to include delayed neutrons follows directly from the multiple collision treatment, as does an equivalence between a monoenergetic time-dependent problem and a particular stationary slowing down problem in infinite geometry. Results are tabulated and comparisons are made to provide benchmark solutions to the fundamental time-dependent transport problems considered and thus bridge the gap between theory and practice.
NUCLEAR SCIENCE AND ENGINEERING
author list (cited authors)
GANAPOL, B. D., MCKENTY, P. W., & PEDDICORD, K. L.
complete list of authors
GANAPOL, BD||MCKENTY, PW||PEDDICORD, KL