Study of Reduced-Enrichment Uranium Fuel Possibility for Research Reactors; MATEC Web of Conferences; Vol. 37 : Smart Grids 2015

Study of Reduced-Enrichment Uranium Fuel Possibility for Research Reactors; MATEC Web of Conferences; Vol. 37 : Smart Grids 2015

Detalles Bibliográficos
Parent link:MATEC Web of Conferences
Vol. 37 : Smart Grids 2015.— 2015.— [01059, 3 p.]
Autor Corporativo: Национальный исследовательский Томский политехнический университет (ТПУ) Энергетический институт (ЭНИН) Кафедра атомных и тепловых электростанций (АТЭС)
Otros Autores: Ruppel V. A., Tretyakova Yu. S., Lavrinenko S. V. Sergey Viktorovich, Matveeva A. A. Anastasiya Aleksandrovna, Martyshev V. N. Vladimir Nikolaevich
Sumario:Title screen
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.
Lenguaje:inglés
Publicado: 2015
Materias:
электронный ресурс
труды учёных ТПУ
обогащенный уран
топливо
исследовательские реакторы
тепловые нейтроны
выгорание
Acceso en línea:http://dx.doi.org/10.1051/matecconf/20153701059
http://earchive.tpu.ru/handle/11683/32669
Formato: Electrónico Capítulo de libro
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=645682

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