Formulas for multiplicity counting rates (singles, doubles, etc.), used for the unfolding of parameters of an unknown sample, can be derived from those for the corresponding factorial moments. So far such rates were derived only for neutrons. The novelty of this paper is related to the derivation of the individual gamma and mixed neutron-gamma detection rates as well as to investigation of the possibilities and actual algorithms for the sample parameter unfolding. Taking the individual gamma and mixed neutron-gamma moments up to third order, together with the neutron moments, there will be nine auto- and cross-factorial moments and corresponding multiplicity rates, as well as a larger number of unknowns than for pure neutron detection. The ...
Neutron multiplicity counting (NMC) techniques are widely used for nuclear materials accountability ...
International audienceNeutron spectrometry is of great significance in different fields as reactors ...
Neutron coincident counting is a useful tool, both to determine the nature of a neutron source and t...
Formulas for multiplicity counting rates (singles, doubles, etc.), used for the unfolding of paramet...
Expressions for neutron and gamma factorial moments are known in the literature. For neutrons, these...
Expressions for neutron and gamma factorial moments have been known in the literature. The neutron f...
The multiplicities, or factorial moments, of the distribution of the number of neutrons emerging fro...
One particular purpose of nuclear safeguards, in addition toaccounting for known materials, is the d...
In nuclear safeguards, estimation of sample parameters using neutron-based non-destructive assay met...
The subject of this thesis is the nondestructive assay (NDA) of nuclear materials. NDA is made possi...
In two earlier papers [1], [2] we investigated the possibility of extracting traditional multiplicit...
The current practice of nondestructive assay (NDA) of fissile materials using neutrons is dominated ...
The multiplicities, or factorial moments, of the distribution of the number of neutrons emerging fro...
Passive methods of nuclear safeguards determine the important parameters of an unknown sample from t...
Neutron coincident counting is a useful tool, both to determine the nature of a neutron source and t...
Neutron multiplicity counting (NMC) techniques are widely used for nuclear materials accountability ...
International audienceNeutron spectrometry is of great significance in different fields as reactors ...
Neutron coincident counting is a useful tool, both to determine the nature of a neutron source and t...
Formulas for multiplicity counting rates (singles, doubles, etc.), used for the unfolding of paramet...
Expressions for neutron and gamma factorial moments are known in the literature. For neutrons, these...
Expressions for neutron and gamma factorial moments have been known in the literature. The neutron f...
The multiplicities, or factorial moments, of the distribution of the number of neutrons emerging fro...
One particular purpose of nuclear safeguards, in addition toaccounting for known materials, is the d...
In nuclear safeguards, estimation of sample parameters using neutron-based non-destructive assay met...
The subject of this thesis is the nondestructive assay (NDA) of nuclear materials. NDA is made possi...
In two earlier papers [1], [2] we investigated the possibility of extracting traditional multiplicit...
The current practice of nondestructive assay (NDA) of fissile materials using neutrons is dominated ...
The multiplicities, or factorial moments, of the distribution of the number of neutrons emerging fro...
Passive methods of nuclear safeguards determine the important parameters of an unknown sample from t...
Neutron coincident counting is a useful tool, both to determine the nature of a neutron source and t...
Neutron multiplicity counting (NMC) techniques are widely used for nuclear materials accountability ...
International audienceNeutron spectrometry is of great significance in different fields as reactors ...
Neutron coincident counting is a useful tool, both to determine the nature of a neutron source and t...