Calculation methodology of fast fission factor in a thermal reactor

This article describes the coefficient of the fast fission, which is part of the formula of «four factors». Considered, to exist at the moment, two methods for calculation of the coefficient of the fast fission in uranium-water tight lattices. Also presents the results of calculations and comparative analysis of the data obtained by two techniques

Calculation methodology of fast fission factor in a thermal reactor

This article describes the coefficient of the fast fission, which is part of the formula of «four factors». Considered, to exist at the moment, two methods for calculation of the coefficient of the fast fission in uranium-water tight lattices. Also presents the results of calculations and comparative analysis of the data obtained by two techniques

Neutron Age Determination in Fast Reactor Materials using the Group Method

The article deals with the methods of identifying fast neutron age in sodium (Na) and uranium-238 (238U); describes the model of advanced and effective fast neutron nuclear reactors (FN), where Na is a coolant while 238U is involved in the fuel cycle in large quantities; justifies the choice of the group method for calculating the neutron age value in the substances mentioned above that can show the accuracy of the used constants for Na and estimate various versions of multilevel description of neutron moderation in 238U – the most powerful resonance absorber of the neutron reactor active zone

Analytical Estimation of the Central Reflector Impact on Thermal Neutron Flux Density in Research Reactors

In this research was shown an analytical assessment of the impact of the central reflector as an example of spherical reactor in one-group approximation. From the external reflector introduced an effective border that simplifies the mathematical problem of critical task. The validation of the research is done just for one of the IRT-T reactor conditions

Analytical Estimation of the Central Reflector Impact on Thermal Neutron Flux Density in Research Reactors

In this research was shown an analytical assessment of the impact of the central reflector as an example of spherical reactor in one-group approximation. From the external reflector introduced an effective border that simplifies the mathematical problem of critical task. The validation of the research is done just for one of the IRT-T reactor conditions