Accuracy analysis of BN-600 power density calculations

• Published in: Atomic energy (New York, N.Y.) Vol. 108; no. 2; pp. 79 - 88
• Main Authors: Blyskavka, A. A., Moiseev, A. V., Semenov, M. Yu, Seregin, A. S., Khomyakov, Yu. S., Tsibulya, A. M., Belov, A. A., Seleznev, E. F., Vasil’ev, B. A., Farakshin, M. R.
• Format: Journal Article
• Language: English
• Published: Boston Springer US 01.06.2010; Springer; Springer Nature B.V
• Subjects: Accuracy; Analysis; Approximation; Assessments; Atomic physics; Density; Errors; Experimental data; Experiments; Hadrons; Heavy Ions; Integrals; Mathematical models; Nuclear Chemistry; Nuclear Energy; Nuclear fuels; Nuclear Physics; Nuclear power plants; Nuclear reactors; Physics; Physics and Astronomy; Reactors; Screens; Specific gravity; Studies; Transport; Fuel Assembly; Fission Rate; Methodological Error; Neutron Field; Boron Carbide
• ISSN: 1063-4258; 1573-8205
• DOI: 10.1007/s10512-010-9260-9

Methodological program techniques for performing neutron-physical calculations of fast-reactor cores with a description of the main codes TRIGEX, JARFR, GEFEST, MMKKENO, and ModExSys are described. The results of verification and assessment of the methodological errors on the basis of a test model of BN-600 are presented. Transport effects and mesh errors in the reaction rate distributions in the core, lateral screen, and in-reactor storage area are evaluated. An integral assessment of the computational accuracy is performed by comparing with the experimental data obtained by γ-scans of BN-600 fuel assemblies. It is shown that calculations describe the experimental data over the core with an error no worse than 5%. In the lateral screen and the in-reactor storage area, the discrepancy between the calculations and experiment does not exceed 20–30%.