Aim of this work is to study the effect of NaCl on neutron flux through graphite block. Graphite block had 39 channels drilled through it and filled with NaCl. Au and In foils and In wire was used for neutron activation measurement of the neutron flux. AmBe neutron source with nominal activity of 92.5 GBq was used. The results were compared with MCNP simulations with channels filled with salt and air. Twelve different locations for Au and In foils were used and In wires were place in three locations to measure vertical profile of neutron flux
International audienceGraphite has been widely used as neutron moderator, reflector or fuel matrix i...
Abstract. Neutron diffusion length in reactor grade graphite is measured both experimentally and the...
Detailed pulsed neutron measurements have been performed in graphite assemblies ranging in size fro...
Master’s thesis focuses on the history and current progress in research of molten salt reactors arou...
Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of the...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
Graphite is a ubiquitous material in nuclear engineering. Within Generation IV designs, graphite ser...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
To meet strong demand for realizing an effective tool to diagnose salt distribution in concrete infr...
The absorption cross sections of low energy neutrons obey 1/v law for most materials. Therefore, the...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
An analysis was made of the nuclear parameters for sodium graphite reactor lattices. These parameter...
In the experimental section of this project, the energy spectrum of fast neutrons is measured, after...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
International audienceGraphite has been widely used as neutron moderator, reflector or fuel matrix i...
Abstract. Neutron diffusion length in reactor grade graphite is measured both experimentally and the...
Detailed pulsed neutron measurements have been performed in graphite assemblies ranging in size fro...
Master’s thesis focuses on the history and current progress in research of molten salt reactors arou...
Several concepts of new reactors use graphite. Some of them use graphite as a moderator, some of the...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
The aim of this paper is to present results of fast neutron behavior analysis within the chloride sa...
Graphite is a ubiquitous material in nuclear engineering. Within Generation IV designs, graphite ser...
Nowadays Gen. IV reactors are attracting more attention, and so the same attention should be given t...
To meet strong demand for realizing an effective tool to diagnose salt distribution in concrete infr...
The absorption cross sections of low energy neutrons obey 1/v law for most materials. Therefore, the...
Presented at the NuMat 2014 Conference, 27–30 October 2014, Clearwater, Florida, USA.International a...
An analysis was made of the nuclear parameters for sodium graphite reactor lattices. These parameter...
In the experimental section of this project, the energy spectrum of fast neutrons is measured, after...
International audienceImpurities in nuclear graphite can become neutron-activated during operation, ...
International audienceGraphite has been widely used as neutron moderator, reflector or fuel matrix i...
Abstract. Neutron diffusion length in reactor grade graphite is measured both experimentally and the...
Detailed pulsed neutron measurements have been performed in graphite assemblies ranging in size fro...