Analysis of fast neutron transport in chloride salts using Monte Carlo method

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

Research outputpeer-review


The aim of this paper is to present results of fast neutron behavior analysis within the chloride salts environment using simulations based on Monte Carlo method (MCNP 6.2). Three non-fueled salts (NaCl, KCl, MgCl2) and two salts containing fissile material (UCl3, ThCl4) were studied. Results of this theoretical study will be used for design of an experimental assembly, which will serve to achieve goals of the international research project ADAR (Accelerator Driven Advanced Reactor). One of the project objectives is to investigate chloride salts as potential coolant and a dissolved fuel carrier of advanced nuclear reactor cooled by molten salts and driven by an accelerator.
Original languageEnglish
Title of host publicationActa Polytechnica CTU Proceedings
PublisherCzech Technical University
Number of pages8
StatePublished - 1 Dec 2020
Event2020 - SIMANE: Student conference on nuclear engineering - Central Library, Prague
Duration: 1 Jun 20202 Jun 2020

Publication series

NameActa Polytechnica - CTU Proceedings
PublisherCzech Technical University
ISSN (Print)1210–2709
ISSN (Electronic)1805–2363


Conference2020 - SIMANE
Abbreviated titleŠimáně2020
Country/TerritoryCzech Republic

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