Corrosion and Deposition of Irradiated Stainless Steel in Sodium.
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A phenomenological model is proposed for fi nding the relationship between the observed behavior of corrosion radionuclides in liquid sodium and the experimental conditions. Reactor and extra-reactor experimental data are used to fi nd the temperature and rate dependences of the model parameters so that the model refl ects a wide range of experimental conditions. Most of the experimental data were obtained using domestic fast reactors and, to a lesser extent, foreign reactors. The design code Al'fa-M, which is based on the proposed model, is described. The code was tested on the BN-600 reactor. It was shown that the proposed modeling approach makes it possible to solve the problem of calculating the removal from the core and the distribution in the tank of a power reactor of activated products of corrosion with satisfactory accuracy within the framework of the problem at hand. In addition, discrepancies between the calculations and experiments, requiring further improvements to the model are found.An important scientifi c and technical problem is the radiation safety of power-generating facilities with large fast reactors, including the reactor itself, the transport-fuel channel and cool-down pool for spent fuel assemblies, and the radwaste repository. The objective of radiation safety is to minimize the effect of sources of ionizing radiation on workers and the surrounding environment.A great deal of experimental information concerning radiation safety and information obtained during operating of facilities with a fast reactor has now been accumulated. Data with different degrees of reliability are now available on approximately 10 reactor facilities, including foreign facilities, and as many sodium stands (Table 1). Many specialists are attempting to generalize the results of reactor experiments and stand tests performed with interconnected models. Methods for using models in integral codes for analysis and validation of the safety of NPP with fast reactors in normal operating and emergency situations are being developed at Institute for Physics and Power Engineering (FEI) and Institute of Problems in the Safe Development of Nuclear Energy (IBRAE).The present article proposes a phenomenological approach to modeling the transport of corrosion radionuclides in a nonisothermal loop, implemented in the design code Alfa-M.Corrosion Rate. The corrosion rate of chromium-nickel steel in sodium is calculated, as a rule, using a relation from [1] with three basic parameters:where O is the oxygen concentration in sodium, ppm; ω is the average sodium fl ow rate, m/sec; and T is the temperature of the laved surface, K. The corrosion rate increases with increasing sodium fl ow rate according to the empirical relation F(ω) = (ω/3) 0.333 . As the sodium velocity increases, the corrosion regime changes: gradually transitioning from the diffusion into the kinetic region, where its effect is very small. The critical velocity of the sodium, at which the kinetic regime of corrosion for chromium-nickel steel starts, equals 3-4 m/sec...
A phenomenological model is proposed for fi nding the relationship between the observed behavior of corrosion radionuclides in liquid sodium and the experimental conditions. Reactor and extra-reactor experimental data are used to fi nd the temperature and rate dependences of the model parameters so that the model refl ects a wide range of experimental conditions. Most of the experimental data were obtained using domestic fast reactors and, to a lesser extent, foreign reactors. The design code Al'fa-M, which is based on the proposed model, is described. The code was tested on the BN-600 reactor. It was shown that the proposed modeling approach makes it possible to solve the problem of calculating the removal from the core and the distribution in the tank of a power reactor of activated products of corrosion with satisfactory accuracy within the framework of the problem at hand. In addition, discrepancies between the calculations and experiments, requiring further improvements to the model are found.An important scientifi c and technical problem is the radiation safety of power-generating facilities with large fast reactors, including the reactor itself, the transport-fuel channel and cool-down pool for spent fuel assemblies, and the radwaste repository. The objective of radiation safety is to minimize the effect of sources of ionizing radiation on workers and the surrounding environment.A great deal of experimental information concerning radiation safety and information obtained during operating of facilities with a fast reactor has now been accumulated. Data with different degrees of reliability are now available on approximately 10 reactor facilities, including foreign facilities, and as many sodium stands (Table 1). Many specialists are attempting to generalize the results of reactor experiments and stand tests performed with interconnected models. Methods for using models in integral codes for analysis and validation of the safety of NPP with fast reactors in normal operating and emergency situations are being developed at Institute for Physics and Power Engineering (FEI) and Institute of Problems in the Safe Development of Nuclear Energy (IBRAE).The present article proposes a phenomenological approach to modeling the transport of corrosion radionuclides in a nonisothermal loop, implemented in the design code Alfa-M.Corrosion Rate. The corrosion rate of chromium-nickel steel in sodium is calculated, as a rule, using a relation from [1] with three basic parameters:where O is the oxygen concentration in sodium, ppm; ω is the average sodium fl ow rate, m/sec; and T is the temperature of the laved surface, K. The corrosion rate increases with increasing sodium fl ow rate according to the empirical relation F(ω) = (ω/3) 0.333 . As the sodium velocity increases, the corrosion regime changes: gradually transitioning from the diffusion into the kinetic region, where its effect is very small. The critical velocity of the sodium, at which the kinetic regime of corrosion for chromium-nickel steel starts, equals 3-4 m/sec...
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