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
This work evaluates several neutronics-related performance characteristics of a proposed molten salt...
Molten salts (fluorides or chlorides) have been taken in consideration very soon in nuclear energy p...
This thesis summarizes an intensive computational study to a proton accelerator-driven thorium-fuele...
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and...
In present study, the model of Molten Salt Reactor was developed for Monte Carlo NParticle Transport...
Aim of this work is to study the effect of NaCl on neutron flux through graphite block. Graphite blo...
Nowadays there is research into molten salt reactors. The use of chlorine-based salts, which would b...
Molten salt reactors (MSRs), as one of the six main technologies of Gen IV, can meet the broad area ...
The thesis deals with the issue of liquid salt reactors, gives information on historical and current...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
paper 9207International audienceEssentially, because the salt is the moderator, the coolant and the ...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
This paper presents a preliminary approach to thermo-hydraulics of the molten salt, which plays the ...
The Molten Salt Reactor (MSR) is a thermal neutron reactor with graphite moderation and operates on ...
The molten salt cooled, graphite moderated Advanced High Temperature Reactor (AHTR) provides an inte...
This work evaluates several neutronics-related performance characteristics of a proposed molten salt...
Molten salts (fluorides or chlorides) have been taken in consideration very soon in nuclear energy p...
This thesis summarizes an intensive computational study to a proton accelerator-driven thorium-fuele...
The master ‘s thesis deals with the studying behavior of nuclear reactors cooled by liquid salts and...
In present study, the model of Molten Salt Reactor was developed for Monte Carlo NParticle Transport...
Aim of this work is to study the effect of NaCl on neutron flux through graphite block. Graphite blo...
Nowadays there is research into molten salt reactors. The use of chlorine-based salts, which would b...
Molten salt reactors (MSRs), as one of the six main technologies of Gen IV, can meet the broad area ...
The thesis deals with the issue of liquid salt reactors, gives information on historical and current...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
paper 9207International audienceEssentially, because the salt is the moderator, the coolant and the ...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
This paper presents a preliminary approach to thermo-hydraulics of the molten salt, which plays the ...
The Molten Salt Reactor (MSR) is a thermal neutron reactor with graphite moderation and operates on ...
The molten salt cooled, graphite moderated Advanced High Temperature Reactor (AHTR) provides an inte...
This work evaluates several neutronics-related performance characteristics of a proposed molten salt...
Molten salts (fluorides or chlorides) have been taken in consideration very soon in nuclear energy p...
This thesis summarizes an intensive computational study to a proton accelerator-driven thorium-fuele...