Degradation of Beryllium Reflector Properties on the IRT-T 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)

Degradation of Beryllium Reflector Properties on the IRT-T 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)

Bibliographic Details
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. 289-293]
Corporate Authors: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра физико-энергетических установок (№ 21) (ФЭУ), Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Лаборатория № 33 ядерного реактора, Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра иностранных языков физико-технического института (ИЯФТ)
Other Authors: Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Varlachev V. A. Valery Aleksandrovich, Anikin M. N. Mikhail Nikolaevich, Chyuykina A., Ermakova Ya. V. Yanina Viktorovna
Summary:Title screen
This paper presents the results of a numerical calculation of beryllium poisoning of an IRT-T reactor and its effect on the excess reactivity and neutron flux density in the beam ports. Also, the prediction of {6}Li and{3}He poison concentrations in the beryllium reflectors of the IRT-T reactor is presented. The results are based on MCU Monte Carlo calculations. The part of reactor history was taken into account to predict reliable values of parasitic isotope concentrations. The impact of shut-down time and operating time on the excess reactivity is shown. The results presented in this paper could be used to perform the safety analysis of an IRT-T reactor.
Режим доступа: по договору с организацией-держателем ресурса
Language:English
Published: 2015
Series:Nuclear Engineering and Fuel Cycles
Subjects:
электронный ресурс
труды учёных ТПУ
реактивность
накопление
гелий
ИРТ-Т
исследовательские реакторы
литий
нейтроны
Online Access:http://dx.doi.org/10.4028/www.scientific.net/AMR.1084.289
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=640323

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