Use of thorium in thermal-neutron reactors: Computation model and comparison of neutronic codes

Abstract

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.

Original language	English
Pages (from-to)	428-431
Number of pages	4
Journal	Journal of Industrial Pollution Control
Volume	32
Issue number	2
Publication status	Published - 2016

Keywords

Neutron-physical computations
Neutronic code
Nuclear fuel cycle
Thermal-neutron reactors
Thorium

ASJC Scopus subject areas

Water Science and Technology
Ocean Engineering
Pollution
Fluid Flow and Transfer Processes
Atmospheric Science

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Naymushin, A., Chertkov, Y. U., Lebedev, I., & Anikin, M. (2016). Use of thorium in thermal-neutron reactors: Computation model and comparison of neutronic codes. Journal of Industrial Pollution Control, 32(2), 428-431.

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abstract = "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.",

keywords = "Neutron-physical computations, Neutronic code, Nuclear fuel cycle, Thermal-neutron reactors, Thorium",

author = "A. Naymushin and Chertkov, {Y. U.} and I. Lebedev and M. Anikin",

year = "2016",

language = "English",

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AU - Anikin, M.

PY - 2016

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AB - 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.

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