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

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6919Article Text2179021020201203.pdf(1.66 MB)
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2020-12-01
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Czech Technical University in Prague
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Abstract
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.
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accelerator driven systems, fast neutrons, ADAR, chloride salts, MCNP, molten salt reactors, Monte Carlo simulations
Citation
Acta Polytechnica CTU Proceedings. 2020, vol. 28, issue 1, p. 42-49.
https://ojs.cvut.cz/ojs/index.php/APP/article/view/6919
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Peer-reviewed
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en
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Creative Commons Attribution 4.0 International
http://creativecommons.org/licenses/by/4.0/
DOI
10.14311/APP.2020.28.0042
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http://hdl.handle.net/11012/196549
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