Приведено краткое описание метода полиномиальной интерполяции нейтронно-физических малогрупповых гомогенизированных констант для реактора ВВЭР-1000. Выполнены расчеты поля энерговыделения активной зоны с применением данного метода для различных моментов времени топливной кампании. Дан сравнительный анализ результатов расчета коэффициентов неравномерности энерговыделения k v и k q с подготовленным константным обеспечением по представленному мет оду при использовании разных программных продуктов.
The accuracy and quality of neutron-physical calculations of the active core characteristics depend heavily on the few-group constant preparation procedure. The method, based on using average in the fuel assembly fuel and coolant parameters is currently used for preparing macroscopic cross-sections. The question is what impact would considering the uneven distribution of those parameters, made on the few-group constant preparation stage exert on further analysis of the reactor facility behavior during steady-state and transients operation. The study carries out comparative analysis of the neutron-physical characteristics of the VVER-1000 core using the standard approach and using distributed in the fuel assembly fuel and coolant parameters while preparing few-group constants. It’s revealed that the fuel pellet and coolant radial temperature distributions affect the multiplication factor and temperature reactivity effect values.
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