|
|
Experimental analysis focused on the effect of chloride salt on neutron flux with different energy levels
Slančík, Tomáš ; Števanka, Kamil (oponent) ; Katovský, Karel (vedoucí práce)
Master’s thesis focuses on the history and current progress in research of molten salt reactors around the world, with an emphasis placed on the properties of molten salts and the problems associated with their use. In relation to the practical part, one chapter is devoted to the creation of input file in the MCNP software. The practical part deals with neutron activation analysis of graphite prism experiment, which is filled with powder NaCl salt. This experiment is focused on the effect of salt on neutron flux with different energy levels. The whole problem was also simulated in the MCNP environment along with the experiment. At the end of the thesis, the individual methods are compared and evaluated.
|
|
| |
|
|
Analysis Of Various Candidate Salts For Molten Salt Reactor Application By Mcnp Software
Petrosyan, Taron
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.
|
|
|
Experimental analysis focused on the effect of chloride salt on neutron flux with different energy levels
Slančík, Tomáš ; Števanka, Kamil (oponent) ; Katovský, Karel (vedoucí práce)
Master’s thesis focuses on the history and current progress in research of molten salt reactors around the world, with an emphasis placed on the properties of molten salts and the problems associated with their use. In relation to the practical part, one chapter is devoted to the creation of input file in the MCNP software. The practical part deals with neutron activation analysis of graphite prism experiment, which is filled with powder NaCl salt. This experiment is focused on the effect of salt on neutron flux with different energy levels. The whole problem was also simulated in the MCNP environment along with the experiment. At the end of the thesis, the individual methods are compared and evaluated.
|
host ::
RSS.