The operation of nuclear reactors requires detailed knowledge of important safety
parameters, such as the spatial power distribution, control rod worth, margin to departure …

Highlights•Current coupling collision probability method with expansion of flux by orthogonal
polynomials is verified.•The Gramm-Schmidt procedure for the orthogonalisation of the two …

This paper focused upon an approach to the promotion of the resonance self-shielding
treatment to overwhelm the reaction rates deviation that mitigating frequent assumption of …

In this paper, we presented an adaptive algorithm for the interface current collision
probability method. The algorithm is based on a posteriori estimation scheme to obtain the …

Adaptive refinement is a powerful method for efficiently solving physical problems. In this
paper we present a new coupled space–angle adaptive algorithm for neutron transport …

In this study, we propose a new method to optimize subgroup parameters for resonance self-
shielding calculation. Our approach integrates the merits of both the subgroup method and …

One of the methods that widely used in solving neutron transport equations in the nuclear
fuel cell is the collision probability (CP) method. The neutron transport is very important to …

In this paper, we investigate and present an adaptive node refinement algorithm driven by
an error estimator for particle transport techniques based on response matrix and collision …

In this study, we applied physical probability table to response matrix-collision probability
method to treat and evaluate self-shielded resonance cross-sections for whole-core …

The Dancoff correction is important in the calculation of the effective cross section of
resonant isotopes in a heterogeneous system. Although the neutron current method is a …