Two correlated Monte Carlo methods, the similar flight path and the identical flight path methods, have been improved to evaluate up to the second order change of the reactivity perturbation. Secondary fission neutrons produced by neutrons having passed through perturbed regions in both unperturbed and perturbed systems are followed in a way to have a strong correlation between secondary neutrons in both the systems. These techniques are incorporated into the general purpose Monte Carlo code MORSE, so as to be able to estimate also the statistical error of the calculated reactivity change.The control rod worths measured in the FCA V-3 assembly are analyzed with the present techniques, which are shown to predict the measured values within the standard deviations. The identical flight path method has revealed itself more useful than the similar flight path method for the analysis of the control rod worth.
Aiming at providing test problems that may be used to verify an adequate performance of the current version of a neutron and 7-ray transport computer code used for reactor core or shield calculations, we summarize the input data and the calculated results for three benchmark problems. The 1st problem deals with a 1-dimensional small spherical reactor for use to test 1-dimensional SN codes, DTF-lV and ANISN, and possibly the MORSE Monte Carlo code. The 2nd problem concerned with 2-dimensional (2, y) neutron propagation through an absorbing medium gives a severe test for 2-dimensional S,V codes, TWOTRAN-GG, TWOTRAN-IT, DOT-3 and TRIPLET. The last problem dealing with 2-dimensional (r, z) radiation streaming is to test also the finite difference SN codes, TWOTRAN-IT and DOT-3, and the finite element S.V code FEMRZ. The present article summarizes also the general tendency of the effect of parameters used for these calculations on the numerical results and computation time.
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