Requirements on the computational accuracy required in the calculation of the neutron-physical characteristics of fast breeder reactors and methods for meeting them

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.The reliability of any safety substantiation of fast reactors is determined by, among other things, the accuracy of the predictions of reactivity effects, which play a key role in transient and accident processes. At present, there are no specific requirements, in the volume needed, for computational accuracy and for improving the computational techniques [1]. The uncertainty in the range of the admissable error makes it difficult to unify the computational codes and make recommendations for using these codes when licensing a reactor. The absence of a standard experimental base of neutron-physical safety parameters for fast reactors makes it necessary to verify the computational codes on test models. To this end, a simplified model of a hybrid (use of uranium and mixed fuel in combination)

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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)

Danilychev

Elistratov

Stogov

et al. 2004

At Energy

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Requirements on the computational accuracy required in the calculation of the neutron-physical characteristics of fast breeder reactors and methods for meeting them

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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)

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)

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