The influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into account by two leakage models named TIBERE and TIBERE-2 These models are founded on the heterogenous Bn theory, that the existence of a fundamental mode in an infinite and regular lattice of identical assemblies of cells, thus enabling that the macroscopic flux, which is periodic and describes fine variations in a perfectly reflected assembly or cell The reason why the simplified heterogenous B1 models TIBERE and TIBERE-2 have been derived is to consider the streaming anisotropy and heterogeneity within a fine flux transport calculation in a consistent manner since the homogenous B1 leakage model is insufficient, especially in cases when a rea...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Neutron transport calculations by Monte Carlo methods are finding increased application in nuclear r...
Few-group cross sections used in nodal calculations derive from standard energy collapsing and spati...
The influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
The influence of assembly or cell heterogeneity on neutron leakage has been consistently taken into ...
This model is based on the heterogeneous B1 theory and accounts for heterogeneous effects on the neu...
The new theoretical method, implemented in APOLLO-2 code as the TIBERE procedure, allows to take int...
This method, which takes into account the influence of assembly heterogeneity on neutron leakage, is...
The growing interest in safety problems had led physicists to try to increase their knowledge of the...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
The flux calculation in a heterogeneous assembly in APOLLO and APOLLO-2 codes is based on the collis...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
Nuclear reactor physics design and analysis requires broad knowledge of parameters affecting reactor...
Modeling spectral effects due to core heterogeneity is one of the major challenges for current nodal...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Neutron transport calculations by Monte Carlo methods are finding increased application in nuclear r...
Few-group cross sections used in nodal calculations derive from standard energy collapsing and spati...
The influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
The influence of assembly or cell heterogeneity on neutron leakage has been consistently taken into ...
This model is based on the heterogeneous B1 theory and accounts for heterogeneous effects on the neu...
The new theoretical method, implemented in APOLLO-2 code as the TIBERE procedure, allows to take int...
This method, which takes into account the influence of assembly heterogeneity on neutron leakage, is...
The growing interest in safety problems had led physicists to try to increase their knowledge of the...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
The flux calculation in a heterogeneous assembly in APOLLO and APOLLO-2 codes is based on the collis...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
Nuclear reactor physics design and analysis requires broad knowledge of parameters affecting reactor...
Modeling spectral effects due to core heterogeneity is one of the major challenges for current nodal...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
ABSTRACT: Due to their complexity, neutronic calculations are usually performed in two steps. Once t...
Neutron transport calculations by Monte Carlo methods are finding increased application in nuclear r...
Few-group cross sections used in nodal calculations derive from standard energy collapsing and spati...