Abstract. 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.
Mathematical model and study techniqueIn the academic literature assessments of the impact of the central reflector is not given [1][2][3]. In some works a crucial problem was solved for planar geometry of the one-group, one-group modified [4] and in the diffusion-age approximation [6][7][8].It should be noted [1][2], that the inner central reflectors are used in the projects of research and power reactors to increase the thermal neutron flux and for the energy alignment on the core of a nuclear reactor. These results can be widely applied in practice, e.g. in solving the acute problem of central reflector masonry beryllium poisoning, (on the example of the IRT-T research reactor). The purpose of this research is to solve the critical problem as an example of a homogeneous spherical reactor with internal and external reflectors in the single-group approximation. To simplify the problem, is used the method of effective boundary conditions, following which from the outside of the reflector introduce efficient frontier R. Graphical interpretation is shown in Figure 1. Article available at
Abstract. The main temperature characteristics of a pressurized water reactor are distinguished, supporting its safety and reliable operation. The special role of the uranium fuel effective temperature is emphasized and the accuracy of the analytical determination of the power effect is increased. The calculation of the temperature distribution along the radius of the fuel rod was carried out taking into account the temperature dependence of the thermal conductivity UO2. The design procedure was corrected for using the Finca-Ronchi dependence for the thermal conductivity of 95% density of the theoretical one.
Abstract. 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.
In this paper, the campaign of RITM-200 reactor was calculated. The duration of the campaign was determined taking the net capacity factor into consideration. The calculated duration concurred with the known data. The neutron parameters were calculated using the effective temperature method. The presence of burnable absorber rods was taken into account. Their effect was considered using the diffusional approach. The iterative computations were used to finally determine the temperature of the neutron gas. At the end, the reactivity curve displaying different effects inside fuel, namely fuel and gadolinium burn-out, the poisoning and slagging was drawn.
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