| Autor: |
El Mtili, A., El Hajjaji, O., El Bardouni, T., El Hlaibi, S. El Maliki, El Yaakoubi, H., Al Zain, J. |
| Předmět: |
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| Zdroj: |
International Journal on Engineering Applications; Jul2023, Vol. 11 Issue 4, p270-277, 8p |
| Abstrakt: |
This article aims to calculate and analyze the reactivity coefficients of a SLOWPOKE-2 reactor under different temperature conditions using the OpenMC code and two cross-sectional libraries, JENDL4.0 and the version VIII.0 of the ENDF/B library. The study focuses on the effect of temperature on the reactivity coefficients, specifically the Fuel Temperature Coefficient (FTC), Moderator Temperature Coefficient (MTC), and Moderator Density Coefficient (MDC), as well as the neutron flux. Through full-core calculations using the three-dimensional Monte Carlo method, the reactivity coefficients and neutron flux for both normal and accidental operating conditions of the SLOWPOKE-2 reactor are determined. The reactor employs Low Enriched Uranium Dioxide (LEU-UO2) with a 19.89% enrichment level. The results of the calculations provide valuable insights into the behavior of the SLOWPOKE-2 reactor under varying temperature conditions. Furthermore, the neutron flux distribution is analyzed, providing information on the spatial distribution of neutrons within the reactor core. The obtained results contribute to the existing knowledge on the thermal behavior of the SLOWPOKE-2 reactor, which is essential for optimizing its performance and ensuring safe operation. Also, the findings can guide future design improvements and safety enhancements in similar research reactor systems. [ABSTRACT FROM AUTHOR] |
| Databáze: |
Complementary Index |
| Externí odkaz: |
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