Neutron Age Determination in Fast Reactor Materials using the Group Method

Bibliographic Details
Parent link:MATEC Web of Conferences
Vol. 72 : Heat and Mass Transfer in the System of Thermal Modes of Energy – Technical and Technological Equipment (HMTTSC-2016).— 2016.— [01040, 8 p.]
Corporate Author: Национальный исследовательский Томский политехнический университет
Other Authors: Kabanova M. F. Marina, Yuzhakov A. V. Aleksey, Kuzmin A. V. Arian Valerievich, Kobenko Yu. V. Yury Viktorovich, Riabova E. S. Elena
Summary:Title screen
The article deals with the methods of identifying fast neutron age in sodium (Na) and uranium-238 (238U); describes the model of advanced and effective fast neutron nuclear reactors (FN), where Na is a coolant while 238U is involved in the fuel cycle in large quantities; justifies the choice of the group method for calculating the neutron age value in the substances mentioned above that can show the accuracy of the used constants for Na and estimate various versions of multilevel description of neutron moderation in 238U – the most powerful resonance absorber of the neutron reactor active zone.
Published: 2016
Subjects:
Online Access:http://dx.doi.org/10.1051/matecconf/20167201040
http://earchive.tpu.ru/handle/11683/33438
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=649905