Abstract
The results of calculations of reactivity effects and analysis of how the computational error affects the course of accidents which involve coolant-flow disturbances and reactivity increases are presented for an IAEA test model — the BN-600 reactor with a hybrid core. It is shown that the solution of the neutron transport equation in the diffusion approximation gives satisfactory accuracy in determining the main reactivity effects for the BN-600 reactor. The reactivity of sodium and steel calculated in the two-dimensional R, Z and three-dimensional HEX, Z geometries and analysis of its effect on the course of a loss-of-coolant accident show that a three-dimensional model gives a lower computational error and, correspondingly, a more accurate description of an accident. Comparative analysis of the results obtained in different countries demonstrated that the methods and programs developed in our country for safety substantiation of fast reactors are reliable.
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Translated from Atomnaya Énergiya, Vol. 97, No. 5, pp. 323–333, November, 2004. Original article submitted October 27, 2003.
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Danilychev, A.V., Elistratov, D.G., Stogov, V.Y. et al. Computational error in calculating reactivity effects in fast reactors and its effect on the assessment of the consequences of the main types of accidents (analysis of the IAEA test model). At Energy 97, 735–743 (2004). https://doi.org/10.1007/s10512-004-0001-9
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DOI: https://doi.org/10.1007/s10512-004-0001-9