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

Другие файлы и ссылки

Fingerprint Подробные сведения о темах исследования «Study of reduced-enrichment uranium fuel possibility for research reactors». Вместе они формируют уникальный семантический отпечаток (fingerprint).

Цитировать

@article{44cbf9a2780a49049148ac2c332ce017,

title = "Study of reduced-enrichment uranium fuel possibility for research reactors",

abstract = "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.",

author = "Ruppel, {V. A.} and Tretyakova, {Yu S.} and Lavrinenko, {S. V.} and Matveeva, {A. A.} and Martyshev, {V. N.}",

year = "2015",

month = dec,

day = "22",

doi = "10.1051/matecconf/20153701059",

language = "English",

volume = "37",

journal = "MATEC Web of Conferences",

issn = "2274-7214",

publisher = "EDP Sciences",

note = "Smart Grids 2015 ; Conference date: 28-09-2015 Through 02-10-2015",

}

TY - JOUR

T1 - Study of reduced-enrichment uranium fuel possibility for research reactors

AU - Ruppel, V. A.

AU - Tretyakova, Yu S.

AU - Lavrinenko, S. V.

AU - Matveeva, A. A.

AU - Martyshev, V. N.

PY - 2015/12/22

Y1 - 2015/12/22

N2 - 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.

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.

UR - http://www.scopus.com/inward/record.url?scp=84976490968&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=84976490968&partnerID=8YFLogxK

U2 - 10.1051/matecconf/20153701059

DO - 10.1051/matecconf/20153701059

M3 - Conference article

AN - SCOPUS:84976490968

VL - 37

JO - MATEC Web of Conferences

JF - MATEC Web of Conferences

SN - 2274-7214

M1 - 01059

T2 - Smart Grids 2015

Y2 - 28 September 2015 through 2 October 2015

ER -