Study of reduced-enrichment uranium fuel possibility for research reactors

V. A. Ruppel, Yu S. Tretyakova, S. V. Lavrinenko, A. A. Matveeva, V. N. Martyshev

Научно-образовательный центр И.Н.Бутакова

Результат исследований: Материалы для журнала › рецензирование

Аннотация

Having analyzed the results obtained in the work, it is possible to conclude that the flux density of fast and thermal neutrons in the shell of fuel elements in EFA in REU-zone decreased on average by 5%for UO2 fuel and by 7%for U9%Mo fuel. Change of neutrons flux density during the cycle does not exceed 4%for both fuel types. On average the fuel burnup in reactor core during the cycle for UO2 and U9%Mo increased by 2.8%. It is 1%less that in HEU-zone, which is conditioned by higher initial loading of 235U in fuel assembly with REU fuel.

Язык оригинала	Английский
Номер статьи	01059
Журнал	MATEC Web of Conferences
Том	37
DOI	https://doi.org/10.1051/matecconf/20153701059
Состояние	Опубликовано - 22 дек 2015
Событие	Smart Grids 2015 - Tomsk, Российская Федерация Продолжительность: 28 сен 2015 → 2 окт 2015

ASJC Scopus subject areas

Chemistry(all)
Engineering(all)
Materials Science(all)

Доступ к документу

10.1051/matecconf/20153701059

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AU - Martyshev, V. N.

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AB - Having analyzed the results obtained in the work, it is possible to conclude that the flux density of fast and thermal neutrons in the shell of fuel elements in EFA in REU-zone decreased on average by 5%for UO2 fuel and by 7%for U9%Mo fuel. Change of neutrons flux density during the cycle does not exceed 4%for both fuel types. On average the fuel burnup in reactor core during the cycle for UO2 and U9%Mo increased by 2.8%. It is 1%less that in HEU-zone, which is conditioned by higher initial loading of 235U in fuel assembly with REU fuel.

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