<abstract xmlns="http://www.w3.org/1999/xhtml">Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad) and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad) cores have been analyzed in this study. The existing HEU core of MNSR was analyzed to validate the neutronic model of reactor, while the LEU core was studied to prove the possibility of fuel conversion of the existing HEU core. The proposed LEU core contained the same number of fuel pins as the HEU core. All other structure materials and dimensions of HEU and LEU cores were the same except the increase in the radius of control rod material from 0.195 to 0.205 cm and keeping the outer diameter of the control rod unchanged in the LEU core. The effective multiplication factor (<italic>keff</italic>), excess reactivity (ρ<italic>ex</italic>), control rod worth (CRW), shutdown margin (SDM), safety reactivity factor (SRF), delayed neutron fraction (β<italic>eff</italic>) and the neutron fluxes in the irradiation tubes for the existing and the potential LEU fuel were investigated. The results showed that the safety parameters and the neutron fluxes in the irradiation tubes of the LEU fuels were in good agreements with the HEU results. Therefore, the LEU fuel was validated to be a suitable choice for fuel conversion of the MNSR in the future.</abstract>

Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad) and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad) cores have been analyzed in this study. The existing HEU core of MNSR was analyzed to validate the neutronic model of reactor, while the LEU core was studied to prove the possibility of fuel conversion of the existing HEU core. The proposed LEU core contained the same number of fuel pins as the HEU core. All other structure materials and dimensions of HEU and LEU cores were the same except the increase in the radius of control rod material from 0.195 to 0.205 cm and keeping the outer diameter of the control rod unchanged in the LEU core. The effective multiplication factor (keff), excess reactivity (ρex), control rod worth (CRW), shutdown margin (SDM), safety reactivity factor (SRF), delayed neutron fraction (βeff) and the neutron fluxes in the irradiation tubes for the existing and the potential LEU fuel were investigated. The results showed that the safety parameters and the neutron fluxes in the irradiation tubes of the LEU fuels were in good agreements with the HEU results. Therefore, the LEU fuel was validated to be a suitable choice for fuel conversion of the MNSR in the future.

Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

Nuclear Engineering Department, Atomic Energy Commission, P. O. Box 6091 Damascus, Syria, Fax: 00963-6111926/7

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This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The...

Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

Publié en ligne: 22 juin 2015

Pages: 367 - 371

Reçu: 16 sept. 2014

Accepté: 06 mars 2015

DOI: https://doi.org/10.1515/nuka-2015-0037

Mots clés
MNSR reactor, HEU fuel, LEU fuel, MCNP4C code, safety parameters

© Saadou Aldawahra et al.

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

Publié en ligne: 22 juin 2015

Pages: 367 - 371

Reçu: 16 sept. 2014

Accepté: 06 mars 2015

DOI: https://doi.org/10.1515/nuka-2015-0037

Mots clésMNSR reactor, HEU fuel, LEU fuel, MCNP4C code, safety parameters

© Saadou Aldawahra et al.

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Mots clés
MNSR reactor, HEU fuel, LEU fuel, MCNP4C code, safety parameters