Use of Thorium in Thermal-Neutron Reactors: Computation Model and Comparison of Neutronic Codes

Use of Thorium in Thermal-Neutron Reactors: Computation Model and Comparison of Neutronic Codes

Bibliographic Details
Parent link:Journal of Industrial Pollution Control
Vol. 32, iss. 2.— 2016.— [P. 428-431]
Corporate Author: Национальный исследовательский Томский политехнический университет (ТПУ) Физико-технический институт (ФТИ) Кафедра физико-энергетических установок (№ 21) (ФЭУ)
Other Authors: Naymushin A. G. Artem Georgievich, Chertkov Yu. B. Yuri Borisovich, Lebedev I. I. Ivan Igorevich, Anikin M. N. Mikhail Nikolaevich
Summary:Title screen
This research is about feasibility study for using thorium-based fuel composition in commercial nuclear power reactors. The article describes comparison of different type of software resources for carrying out neutronic computations for reactor core. To carry out neutronphysical computations the following software resources were chosen: MCU-PTR, WIMSD- 5B, WIMS-ANL. Results of research show that precision software MCU-PTR (Monte Carlo method) demonstrates most accuracy results of calculations. WIMS-family software can be used only for estimated calculations because of its one-dimensional geometrical model. However, isotopic concentrations in fuel assembles during fuel cycle are correct for all of three software. Moreover, showed software allow calculate changes of reactivity margin.
Published: 2016
Subjects:
электронный ресурс
труды учёных ТПУ
торий
реакторы на тепловых нейтронах
ядерно-топливный цикл
нейтроны
thorium
thermal-neutron reactors
neutron-physical computations
nuclear fuel cycle
neutronic code
Online Access:http://www.icontrolpollution.com/articles/use-of-thorium-in-thermalneutron-reactors-computation-model-and-comparison-of-neutronic-codes-.php?aid=79287
Format: Electronic Book Chapter
KOHA link:https://koha.lib.tpu.ru/cgi-bin/koha/opac-detail.pl?biblionumber=655147

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