Development of Calculation Technique for Iterated Fission Probability and Reactor Kinetic Parameters Using Continuous-Energy Monte Carlo Method

Abstract

New algorithms and techniques are developed for calculating the iterated fission probability (IFP ) using a Monte Carlo eigenvalue calculation scheme. The proportionality of the calculated IFP to the adjoint flux is confirmed numerically. This IFP is then used with the MCNP code and its point-wise cross section data libraries to calculate kinetic parameters weighted by the adjoint flux. Experimental data for critical cores validate these theoretical estimates.