Monte Carlo calculations of fast neutron transport in chloride salts

Ondrej Stastny, Dusan Kral, Kamil Stevanka, Karel Katovsky, Antonin Krása

Research outputpeer-review

Abstract

The purpose of this study is to provide data for optimization of an experimental campaign that is under preparation within the frame of the ADAR project (Accelerator Driven Advanced Reactor with molten chloride salt fuel coolant). This article presents results of theoretical investigation of fast neutron field behavior in chloride salt environment. Non-fueled salt coolant (NaCl, KCl, MgCl2) as well as subcritical fuel-containing (PuCl3) one were considered. As an external neutron source, the radio-isotope AmBe source was modelled. Monte Carlo calculations were performed using the MCNP6.2 code with the ENDF/B-VIII.0 and JEFF-3.3 nuclear data libraries.

Original languageEnglish
Title of host publicationProceedings - 2020 21st International Scientific Conference on Electric Power Engineering, EPE 2020
EditorsZdenek Muller, Miroslav Muller
PublisherIEEE - Institute of Electrical and Electronics Engineers
Number of pages6
ISBN (Electronic)9781728194790
DOIs
StatePublished - 19 Oct 2020
Event21st International Scientific Conference on Electric Power Engineering, EPE 2020 - Prague
Duration: 19 Oct 202021 Oct 2020

Publication series

NameProceedings - 2020 21st International Scientific Conference on Electric Power Engineering, EPE 2020

Conference

Conference21st International Scientific Conference on Electric Power Engineering, EPE 2020
Country/TerritoryCzech Republic
CityPrague
Period2020-10-192020-10-21

ASJC Scopus subject areas

  • Hardware and Architecture
  • Energy Engineering and Power Technology
  • Renewable Energy, Sustainability and the Environment
  • Electrical and Electronic Engineering
  • Control and Optimization

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