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

A. Naymushin, Y. U. Chertkov, I. Lebedev, M. Anikin

Research output: Contribution to journalArticle

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 languageEnglish
Pages (from-to)428-431
Number of pages4
JournalJournal of Industrial Pollution Control
Volume32
Issue number2
Publication statusPublished - 2016

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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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