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

Fingerprint

Thorium
thorium
Neutrons
software
Reactor cores
Nuclear energy
Monte Carlo methods
nuclear power
resource
feasibility study
Hot Temperature
reactor
comparison
code
Chemical analysis

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

Cite this

Use of thorium in thermal-neutron reactors : Computation model and comparison of neutronic codes. / Naymushin, A.; Chertkov, Y. U.; Lebedev, I.; Anikin, M.

In: Journal of Industrial Pollution Control, Vol. 32, No. 2, 2016, p. 428-431.

Research output: Contribution to journalArticle

@article{91826bf3b0054ee891c12e8cc2bb5554,
title = "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.",
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",
volume = "32",
pages = "428--431",
journal = "Journal of Industrial Pollution Control",
issn = "0970-2083",
publisher = "Enviro Media",
number = "2",

}

TY - JOUR

T1 - Use of thorium in thermal-neutron reactors

T2 - Computation model and comparison of neutronic codes

AU - Naymushin, A.

AU - Chertkov, Y. U.

AU - Lebedev, I.

AU - Anikin, M.

PY - 2016

Y1 - 2016

N2 - 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.

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.

KW - Neutron-physical computations

KW - Neutronic code

KW - Nuclear fuel cycle

KW - Thermal-neutron reactors

KW - Thorium

UR - http://www.scopus.com/inward/record.url?scp=85014069879&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85014069879&partnerID=8YFLogxK

M3 - Article

AN - SCOPUS:85014069879

VL - 32

SP - 428

EP - 431

JO - Journal of Industrial Pollution Control

JF - Journal of Industrial Pollution Control

SN - 0970-2083

IS - 2

ER -