Original title:
Analysis Of Various Candidate Salts For Molten Salt Reactor Application By Mcnp Software
Authors:
Petrosyan, Taron Document type: Papers
Language:
eng Publisher:
Vysoké učení technické v Brně, Fakulta elektrotechniky a komunikačních technologií Abstract:
In present study, the model of Molten Salt Reactor was developed for Monte Carlo NParticle Transport [1] computational code analysis. In the course of work, two main tasks were fulfilled, which are simulation of target material behavior as a neutron convertor (producer) under 800MeV energy proton beam and criticality calculation of the designed reactor. As a result of analysis through the MCNP software, neutron flux, as well as the value of 𝑘𝑒𝑓𝑓 multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.
Keywords:
criticality; MCNP; Molten Salt Reactor; Thorium Host item entry: Proceedings I of the 26st Conference STUDENT EEICT 2020: General papers, ISBN 978-80-214-5867-3
Institution: Brno University of Technology
(web)
Document availability information: Fulltext is available in the Brno University of Technology Digital Library. Original record: http://hdl.handle.net/11012/200611