Development of the code CYCLE for nuclear fuel cycle analysis

Kalashnikov, Alexandr Grigor’evich; Moseev, A; Dekusar, V. M.; Korobeynikov, V. V.; Moseev, Pavel Andreevich

doi:10.26583/npe.2016.1.10

Cited by 8 publications

(1 citation statement)

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“…Расчеты накопления МА российской ЯЭ в течение текущего столетия сделаны в АО «ГНЦ РФ -ФЭИ» [14] на основании проведенных сценарных исследований с исполь зованием компьютерного кода CYCLE [19,20]. Код предназначен для математическо го моделирования ядерного топливного цикла с реакторами различного типа с уче том изменения изотопного состава ядерных материалов на всех этапах цикла.…”

Section: сценарии накопления минорных актинидовunclassified

Some Economic Aspects of Reducing Americium Production in a Two-Component System of Thermal and Fast Reactors

Gulevich,

Usanov,

Dekusar

et al. 2023

YadEn

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Section: сценарии накопления минорных актинидовunclassified

Some Economic Aspects of Reducing Americium Production in a Two-Component System of Thermal and Fast Reactors

Gulevich,

Usanov,

Dekusar

et al. 2023

YadEn

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The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System

et al. 2022

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On plutonium-241 and americium in the two-component nuclear energy system

Troyanov,

Gulevich,

Gurskaya

et al. 2024

NUCET

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The paper deals with the influence of the strategy for using separated plutonium from spent fuel of thermal and fast reactors, as well as homogeneous burning of americium in the BN reactor core on the balance of americium in the Russian nuclear fuel cycle throughout the 21st century. The assessment is carried out with the use of mathematical modeling of nuclear materials movement including nuclide transformations throughout the nuclear energy system based on the CYCLE code. Scenario modeling of the americium and Pu-241 accumulation was carried out in Russia’s two-component nuclear energy system model with thermal (VVER) and fast (BN) reactors. In so doing, spent nuclear fuel (SNF) reprocessing was simulated in 2 options: as priority reprocessing of SNF of VVER reactors (1) or SNF of BN reactors (2). In addition to americium accumulation in the system without burning, the accumulation of this actinide was studied taking into account its homogeneous burning in the MOX-fuel of fast reactors at the level of its equilibrium content of ~1%. It has been shown that the priority reprocessing of VVER spent fuel makes it possible to reduce the americium accumulation by the end of the century by ~8 tons, and the effect is achieved by using freshly separated plutonium with short-term cooling, thus, by priority the americium source is eliminated, without directly handling it. Homogeneous addition of americium to the fuel of fast reactors of the BN-1200 type at a level of ~1% makes it possible to stop accumulation of americium in a two-component energy system by 2070, stabilizing it at a level of ~40 tons in the scenario with priority reprocessing of VVER SNF and ~50 tons in the scenario with priority reprocessing of BN SNF.

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Development of the code CYCLE for nuclear fuel cycle analysis

Cited by 8 publications

References 0 publications

Some Economic Aspects of Reducing Americium Production in a Two-Component System of Thermal and Fast Reactors

Some Economic Aspects of Reducing Americium Production in a Two-Component System of Thermal and Fast Reactors

The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System

On plutonium-241 and americium in the two-component nuclear energy system

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