This paper presents two separate nuclear data related features recently implemented in the Serpent Monte Carlo reactor physics burnup calculation code. Probability table sampling in the unresolved resonance region was included to improve the modelling capabilities, especially for fast spectrum systems. The procedure follows standard ENDF reaction laws for ACE format cross section data. The practical implementation of the sampling routine, however, required some additional effort, due to the internal unionized energy grid format and the Woodcock delta-tracking method used by the Serpent code. The second new feature is a built-in Doppler broadening routine that allows the temperatures of point-wise cross sections to be adjusted above their original values.
- monte carlo
- probability table