TY - GEN
T1 - A 1D monoenergetic neutron transport benchmark in an infinite medium
AU - Ganapol, Barry D.
N1 - Publisher Copyright:
Copyright © 2014 by ASME.
PY - 2014
Y1 - 2014
N2 - Analytical or semi-analytical benchmarks for the neutron transport equation are relatively infrequent. Some may argue they are no longer necessary because of the enormous computing power and computational technology that is now available. While to some extent true, they can still provide valuable code verification and also serve to teach theoretical and numerical transport methods not taught by executing MATLAB, MAPLE or MATHEMATICA programs or Monte Carlo simulations. The focus of this presentation is on a new analytical solution technique for the solution of the 1D, monoenergetic Green's function for neutron transport. In this formulation, we consider the analytical solution to a threeterm recurrence for flux moments resulting in a semianalytical benchmark. We then apply the benchmark to assess the accuracy of the PN approximation leading to a rather unexpected result.
AB - Analytical or semi-analytical benchmarks for the neutron transport equation are relatively infrequent. Some may argue they are no longer necessary because of the enormous computing power and computational technology that is now available. While to some extent true, they can still provide valuable code verification and also serve to teach theoretical and numerical transport methods not taught by executing MATLAB, MAPLE or MATHEMATICA programs or Monte Carlo simulations. The focus of this presentation is on a new analytical solution technique for the solution of the 1D, monoenergetic Green's function for neutron transport. In this formulation, we consider the analytical solution to a threeterm recurrence for flux moments resulting in a semianalytical benchmark. We then apply the benchmark to assess the accuracy of the PN approximation leading to a rather unexpected result.
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U2 - 10.1115/ICONE22-30156
DO - 10.1115/ICONE22-30156
M3 - Conference contribution
AN - SCOPUS:84911897623
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory
PB - American Society of Mechanical Engineers (ASME)
T2 - 2014 22nd International Conference on Nuclear Engineering, ICONE 2014
Y2 - 7 July 2014 through 11 July 2014
ER -