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

書誌詳細
Parent link:	MATEC Web of Conferences Vol. 37 : Smart Grids 2015.— 2015.— [01059, 3 p.]
団体著者:	Национальный исследовательский Томский политехнический университет (ТПУ) Энергетический институт (ЭНИН) Кафедра атомных и тепловых электростанций (АТЭС)
その他の著者:	Ruppel V. A., Tretyakova Yu. S., Lavrinenko S. V. Sergey Viktorovich, Matveeva A. A. Anastasiya Aleksandrovna, Martyshev V. N. Vladimir Nikolaevich
要約:	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.
言語:	英語
出版事項:	2015
主題:	электронный ресурс труды учёных ТПУ обогащенный уран топливо исследовательские реакторы тепловые нейтроны выгорание
オンライン･アクセス:	http://dx.doi.org/10.1051/matecconf/20153701059 http://earchive.tpu.ru/handle/11683/32669
フォーマット:	MixedMaterials 電子媒体図書の章
KOHA link:	https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=645682

インターネット

http://dx.doi.org/10.1051/matecconf/20153701059
http://earchive.tpu.ru/handle/11683/32669