The influence of assembly or cell heterogeneity on neutron leakage has been consistently taken into account in the TIBERE simplified heterogeneous B1 model The assumption adopted within the TIBERE model that neutrons are specularly reflected on the boundary introduces two problems Calculations with this model may become rather time consuming and even unnecessarily long in the case of a Canada deuterium uranium reactor cell, and the peripheral or total coolant voiding of a pressurized water reactor assembly leads to infinite leakage coefficients These problems have been overcome by the development of another simplified heterogeneous B1 leakage model, TIBERE-2, which has quasi-isotropic reflecting boundary conditions The TIBERE-2 model uses s...
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...
The AGENT code methodology was extended to include the ability to simulate the neutronics of the Ver...
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 influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
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 flux calculation in a heterogeneous assembly in APOLLO and APOLLO-2 codes is based on the collis...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
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 ...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
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...
The AGENT code methodology was extended to include the ability to simulate the neutronics of the Ver...
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 influence of nuclear reactor core lattice heterogeneity on neutron leakage has been taken into a...
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 flux calculation in a heterogeneous assembly in APOLLO and APOLLO-2 codes is based on the collis...
The standard procedure for the calculation of neutron leakage rate of an assembly is based on calcul...
When calculations of flux are done in less than three dimensions, leakage-absorption cross sections ...
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 ...
The author of this paper recently proposed a Monte Carlo calculation algorithm to solve a complex tr...
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...
The AGENT code methodology was extended to include the ability to simulate the neutronics of the Ver...