MATEC Web Conf.
Volume 72, 2016Heat and Mass Transfer in the System of Thermal Modes of Energy – Technical and Technological Equipment (HMTTSC-2016)
|Number of page(s)||8|
|Published online||09 August 2016|
Neutron Age Determination in Fast Reactor Materials using the Group Method
1 National Research Tomsk Polytechnic University, 634050 Tomsk, Russia
2 Samara State Social-Pedagogical University, 443099 Samara, Russia
* Corresponding author: email@example.com
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.
© The Authors, published by EDP Sciences, 2016
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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