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ŠŤASTNÝ, O. KRÁL, D. ŠTEVANKA, K. KATOVSKÝ, K. KRÁSA, A.
Original Title
Monte Carlo Calculations of Fast Neutron Transport in Chloride Salts
Type
conference paper
Language
English
Original 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.
Keywords
fast neutron; chloride salt; molten-salt reactors; Monte Carlo; MCNP; nuclear data
Authors
ŠŤASTNÝ, O.; KRÁL, D.; ŠTEVANKA, K.; KATOVSKÝ, K.; KRÁSA, A.
Released
19. 10. 2020
Publisher
Institute of Electrical and Electronics Engineers Inc.
Location
New York
ISBN
978-1-7281-9479-0
Book
Proccedings of the 2020 21th International Scientific Conference on Electric Power Engineering (EPE)
Edition
1
Edition number
Pages from
344
Pages to
349
Pages count
6
URL
https://ieeexplore.ieee.org/document/9269228
BibTex
@inproceedings{BUT165001, author="Ondřej {Šťastný} and Dušan {Král} and Kamil {Števanka} and Karel {Katovský} and Antonín {Krása}", title="Monte Carlo Calculations of Fast Neutron Transport in Chloride Salts", booktitle="Proccedings of the 2020 21th International Scientific Conference on Electric Power Engineering (EPE)", year="2020", series="1", number="1", pages="344--349", publisher="Institute of Electrical and Electronics Engineers Inc.", address="New York", doi="10.1109/EPE51172.2020.9269228", isbn="978-1-7281-9479-0", url="https://ieeexplore.ieee.org/document/9269228" }