Study of Neutronic and Temperature Distribution During Enrichment Reduction for BN-350 Reactor

Jamal Mohammed Rashid Abda

doi:10.29196/jubpas.v26i8.1681

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Published: 15-10-2018

DOI: https://doi.org/10.29196/jubpas.v26i8.1681

Keywords:

BN-350, Enrichment, Fuel rod, multiplication factor keff, neutron lifetime

Jamal Mohammed Rashid Abda

Department of Physics, College of science, University of Sulaimany

Abstract

This paper represents the neutronic and thermal-hydraulic calculations for the conversion of BN-350 from 27% to 7% enriched Uranium fuel elements. Mixed enrichment cores have been studied where low enrichment uranium (LEU) cores fresh fuel elements substitute gradually the high enrichment uranium (HEU) depleted fuel elements in the equilibrium core.

Thermal-hydraulic calculations have been carried out to determine changes in the characteristics of the converted reactor during steady-state conditions and transient response to a coolant flow loss.

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Vol. 26 No. 8 (2018)

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Articles

How to Cite

[1]

“Study of Neutronic and Temperature Distribution During Enrichment Reduction for BN-350 Reactor”, JUBPAS, vol. 26, no. 8, pp. 151–156, Oct. 2018, doi: 10.29196/jubpas.v26i8.1681.

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