Cross-Verification of the Neutron-Physical Codes CORNER and MCU-FR on Models of Advanced Fast Neutron Reactors
3/28/2023 2023 - #01 Modelling processes at nuclear facilities
Bereznev V.P. Koltashev D.A. Shurygin R.E.
The article considers the cross-verification results for deterministic code CORNER based on the method of discrete ordinates and precision code MCU-FR based on Monte Carlo methods based on lead and sodium-cooled reactor core models. The work relevance is due to the need to conduct cross-verification due to the lack of experiments for designed reactors when certifying a new version of the code. For this, test models of cores (cores) of a lead-cooled fast reactor and a sodium-cooled fast reactor were prepared. Calculations of integral characteristics: control rods efficiency, void reactivity and Doppler effect, reactivity margin and the effective delayed neutron fraction are performed for lead- and sodium-cooled fast neutron reactors core models. Also power distributions calculated by both codes are compared. According to the calculation results the maximum deviation of the control rods efficiency does not exceed 8% for the sodium-cooled reactor core model and 4% for the lead-cooled one. The deviation of the Doppler coefficients does not exceed 3.6% for the lead-cooled model and 6.8% for the sodium-cooled one. The maximum power deviation is 3.1% for the lead-cooled model and 5.9% for the sodium-cooled one. The reactivity margin deviation does not exceed 1.9% for the lead-cooled model and 2.7% for the sodium-cooled one. The maximum deviation of the effective delayed neutron fraction is 1.3% for the lead-cooled model and 0.54% for the sodium-cooled one. Materials for CORNER code certification are prepared based on this work.
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CORNER MCU-FR cross-verification sodium cooled fast reactor lead-cooled fast reactor neutron-physical characteristics
Link for citing the article: Bereznev V.P., Koltashev D.A., Shurygin R.E. Cross-Verification of the Neutron-Physical Codes CORNER and MCU-FR on Models of Advanced Fast Neutron Reactors. Izvestiya vuzov. Yadernaya Energetika. 2023, no. 1, pp. 132-143; DOI: https://doi.org/10.26583/npe.2023.1.11 (in Russian).