Publication detail

Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software

PETROSYAN, T. MELYAN, E. KATOVSKÝ, K.

Original Title

Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software

Type

conference paper

Language

English

Original Abstract

In the study, the model of Molten Salt Reactor was developed for Monte Carlo N-Particle Transport 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 and energy distributions obtained, as well as the value of multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed

Keywords

Molten Salt Reactor; MCNP; criticality; thorium

Authors

PETROSYAN, T.; MELYAN, E.; KATOVSKÝ, K.

Released

19. 10. 2020

ISBN

978-1-7281-9479-0

Book

Proccedings of the 2020 21th International Scientific Conference on Electric Power Engineering (EPE)

Edition

1

Edition number

1

Pages from

293

Pages to

298

Pages count

6

BibTex

@inproceedings{BUT164689,
  author="Taron {Petrosyan} and Elmira {Melyan} and Karel {Katovský}",
  title="Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software",
  booktitle="Proccedings of the 2020 21th International Scientific Conference on Electric Power Engineering (EPE)",
  year="2020",
  series="1",
  number="1",
  pages="293--298",
  isbn="978-1-7281-9479-0"
}