Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 168 / Number 3
Brian C. Kiedrowski, Forrest B. Brown, Paul P. H. Wilson
Nuclear Science and Engineering
Volume 168 / Number 3 / July 2011 / Pages 226-241
Format:electronic copy (download)
A Monte Carlo method is developed that performs adjoint-weighted tallies in continuous-energy k-eigenvalue calculations. Each contribution to a tally score is weighted by an estimate of the relative magnitude of the fundamental adjoint mode, by way of the iterated fission probability, at the phase-space location of the contribution. The method is designed around the power iteration method such that no additional random walks are necessary, resulting in a minimal increase in computational time. The method is implemented in the Monte Carlo N-Particle (MCNP) code. These adjoint-weighted tallies are used to calculate adjoint-weighted fluxes, point reactor kinetics parameters, and reactivity changes from first-order perturbation theory. The results are benchmarked against discrete ordinates calculations, experimental measurements, and direct Monte Carlo calculations.
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