Assessment of Various Candidate Salts Properties for Molten Salt Reactor Application by MCNP Software
2020 21st International Scientific Conference on Electric Power Engineering (EPE)(2020)
摘要
In the study, the model of Molten Salt Reactor was developed for Monte Carlo N-Particle 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 800 MeV 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 k
eff
multiplication factor of Molten Salt Reactor for a number of different molten salts compositions assessed.
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关键词
Molten Salt Reactor,MCNP,criticality,thorium
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