Development Of A Neutronic Model Of The Wwer-1000 Reactor Facility Core

Abstract

A neutronic model of the WWER-1000 reactor has been developed. The reactor block of the B-320 series, which is the most common among NPPs with the WWER type reactors, was selected for the modeling. The modeling was performed using the MCNP6 software. A three-dimensional model of the core has been developed, which fully corresponds to the reactor plant, both in terms of geometric parameters and material composition. The fuel assemblies and rods of the reactor control and protection system have been assembled into appropriate groups. The following opportunities have been implemented in the neutronic model: modeling of various critical reactor states; reactor power control; boron control; efficiency of individual rods and their groups. Preliminary calculations have been performed to substantiate the model operability. The integral and differential efficiency of the control protection systems, temperature feedback of reactivity, the Doppler coefficient, coolant density and boric acid concentration have been also studied.

Recommended Citation

Seken, D.M.; Surayev, A.S.; Irkimbekov, R.A.; Vityuk, G.A.; Mukhamedov, N.Y.; Zhanbolatov, O.M.; and Vityuk, V.A. (2025) "Development Of A Neutronic Model Of The Wwer-1000 Reactor Facility Core," Eurasian Journal of Physics and Functional Materials: Vol. 9: No. 2, Article 6.
DOI: https://doi.org/10.69912/2616-8537.1248