摘要：The VVER reactor investigation is an important goal for Ukrainian nuclear energy. Different deterministic and stochastic codes are using for this purpose. With taking into account the fast development of computer systems, there is a possibility for active using stochastic codes (based on Monte-Carlo method) for simulation of complicated reactor systems. The investigation for implementation of Monte-Carlo code to calculate whole reactor VVER-1000 core was presented in this article. Such type of calculations would be a base for preparation of “information support data” with high accuracy deterministic code for in core monitoring system. The “information support data” includes group constants, coefficients for calculations of model currents, albedo boundary conditions for radial and axial reflectors. The paper presents the use of the new Monte-Carlo Serpent code for the three-dimensional modelling of the VVER-1000 reactor core. The use of Monte-Carlo codes offers an opportunity to analyze the properties of a wide range of the neutron-physical and thermal-hydraulic characteristics at any reactor point. In the work, core models were developed for the Rivne NPP4 first loading and the South-Ukraine NPP3 28th loading. At the same time, assembly models of various manufacturers were prepared. During the core model developing, considerable attention was paid to the upper, lower and side reflectors for detailed modelling. The Monte-Carlo Serpent code validation calculations for the VVER-1000 reactor were performed based on the Rivne NPP4 first loading. The albedo boundary conditions for radial and axial reflectors were obtained for the South-Ukraine NPP3 28th loading. The prepared VVER-1000 reactor core models will use for “information support data” calculations for new Ukrainian In-core monitoring system deterministic code – ImCore, which is under development at PJSC “SRPA “Impulse”. Using computer code based on Monte-Carlo method will provide an opportunity for increasing accuracy of “information support data” and as a consequence, increase the accuracy for VVER-1000 reactor calculations in In-core monitoring system.
其他摘要：Дослідження реакторів ВВЕР є важливою задачею для вітчизняної атомної енергетики. Для цього використовуються різні детерміністичні та стохастичні коди. Із значним прогресом в розвитку комп’ютерних систем з’явилась можливість активного використання стохаст
关键词：nuclear reactor;VVER-1000;calculation of nuclear reactor;Monte Carlo method;core modeling
其他关键词：ядерний реактор;ВВЕР-1000;розрахунок ядерного реактора;Монте-Карло метод;моделювання активної зони
