Calculating kinetics parameters and reactivity changes with continuous-energy Monte Carlo
Conference
·
OSTI ID:973183
- Los Alamos National Laboratory
- UNIV. WISCONSIN
The iterated fission probability interpretation of the adjoint flux forms the basis for a method to perform adjoint weighting of tally scores in continuous-energy Monte Carlo k-eigenvalue calculations. Applying this approach, adjoint-weighted tallies are developed for two applications: calculating point reactor kinetics parameters and estimating changes in reactivity from perturbations. Calculations are performed in the widely-used production code, MCNP, and the results of both applications are compared with discrete ordinates calculations, experimental measurements, and other Monte Carlo calculations.
- Research Organization:
- Los Alamos National Laboratory (LANL)
- Sponsoring Organization:
- DOE
- DOE Contract Number:
- AC52-06NA25396
- OSTI ID:
- 973183
- Report Number(s):
- LA-UR-09-06786; LA-UR-09-6786
- Country of Publication:
- United States
- Language:
- English
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