Feasibility Study of Using New Fuel Composition in IRT-T Research Reactor; Advanced Materials Research : Radiation and nuclear techniques in material science; Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014)

Λεπτομέρειες βιβλιογραφικής εγγραφής
Parent link:Advanced Materials Research : Radiation and nuclear techniques in material science: Scientific Journal
Vol. 1084 : Physical-Technical Problems of Nuclear Science, Energy Generation, and Power Industry (PTPAI -2014).— 2015.— [P. 306-308]
Συλλογικό Έργο: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра физико-энергетических установок (№ 21) (ФЭУ), Томский политехнический университет Институт кибернетики, ИК, Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра иностранных языков физико-технического института (ИЯФТ)
Άλλοι συγγραφείς: Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Kurganov V. V. Vasiliy Vasilievich, Lebedev I. I. Ivan Igorevich, Mongush S. A., Daneykina (Daneikina) N. V. Natalia Viktorovna
Περίληψη:Title screen
The results of simulation of IRT-T reactor conversion from highly enriched fuel to new perspective low enriched fuel based on uranium-molybdenum alloy are given. Main characteristics of reacting core with the use of highly enriched and low enriched fuel are calculated. It is shown that impact of using new materials in fuel composition remains neutronic and thermal hydraulic characteristics of the core at an acceptable level.
Режим доступа: по договору с организацией-держателем ресурса
Γλώσσα:Αγγλικά
Έκδοση: 2015
Σειρά:Nuclear Engineering and Fuel Cycles
Θέματα:
Διαθέσιμο Online:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.306
Μορφή: Ηλεκτρονική πηγή Κεφάλαιο βιβλίου
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640329
Περιγραφή
Περίληψη:Title screen
The results of simulation of IRT-T reactor conversion from highly enriched fuel to new perspective low enriched fuel based on uranium-molybdenum alloy are given. Main characteristics of reacting core with the use of highly enriched and low enriched fuel are calculated. It is shown that impact of using new materials in fuel composition remains neutronic and thermal hydraulic characteristics of the core at an acceptable level.
Режим доступа: по договору с организацией-держателем ресурса
DOI:10.4028/www.scientific.net/AMR.1084.306