By calculation methods, the dose rate of the radioactive waste, behind concrete protection, was evaluated in current work. Parameters, which were taken in account in the calculations, are geometry of the protection shell, size of the source and its isotopic composition. As model geometrical parameters the spent fuel assembly's size and thickness of the concrete wall of the ventilated storage container (VSC)-VVER were taken. The computer program that does numerical calculation was composed in the Wolfram Alpha environment. The program takes into account change of the isotopic composition and spectra of gamma-radiation with time. Calculation results were compared to the known data on the spent nuclear fuel heat dissipation. Approach described in this work can be used for fast estimation of change in the quality of radioactive waste (RAW) in the long-term storage without recycling, for different initial isotopic composition. Obtained results were analyzed on the matter of change in gamma-radiation of RAW. В данной работе численными методами рассчитывалась мощность дозы излучения радиоактивных отходов за бетонной защитой. При расчётах учитывались геометрия защитной оболочки, размер источника и его изотопный состав. В качестве модельных геометрических параметров были взяты размеры отработанной тепловыделяющей сборки (ОТВС) и толщина стенки бетонного вентилируемого контейнера хранения (ВКХ)-ВВЭР. Для проведения численных расчётов, в среде Wolfram Alpha была составлена программа. В программе учитывается изменение изотопного состава отработанного ядерного топлива со временем и изменение энергетического спектра гамма-излучения. Проведено сравнение результатов вычисления с известными данными по тепловыделению отработанного ядерного топлива (ОЯТ). Используемая методика позволяет проводить быструю оценку изменения качества радиоактивных отходов (РАО) при долговременном хранении без переработки, для различных изотопных составов топлива. По результатам расчётов был проведён анализ изменения гамма-излучения РАО. КЛЮЧЕВЫЕ СЛОВА: радиоактивные отходы, мощность дозы, долгосрочное хранение, бетонная защита, изотопный состав KEYWORDSProduction and accumulation of the radioactive waste (RAW) are one of the major problems associated with the use of nuclear energy in any of its forms. According to the existing data, there is about 300 thousand tons of accumulated spent nuclear fuel (SNF) with total activity of ~10 20 Bk, and by year 2030, this quantity is predicted to be 500 thousand tons. In particular, importance of this problem is reflected by the fact, that in the last years several monographs [1][2][3][4][5] on the problems of dealing with RAW were published.Leaving aside the cosmic origin and associated with uranium mining radionuclides, in this paper we will consider 2 forms of RAW: 1) contained in SNF; 2) the so-called operational waste of nuclear plant. According to the established terminology, in countries, where radiochemical or other recycling is not intended (for example -Ukraine), it belongs to the high-level RAW (HLW).
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