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Study.of Criticality.Safety.and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LEU Core Using MCNP Code

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World Journal of Nuclear Science and Technology 2014年第1期4卷 46-52页

作者： Henry.Cecil Odoi Edward H. K. Akaho Sunday.A. Jonah Rex Gy.abour Abrefah viva y. ibrahim Centre for Energy.Research and Training Ahmadu Bello University Zaria Nigeria National Nuclear Research Institute Ghana Atomic Energy Commission Accra Ghana

The National Nuclear Research Institute of the Ghana Atomic Energy.Commission is undertaking steps to convert the Ghana Research Reactor-1 from HEU Core to LEU. The proposed LEU core consists of 12.5% enriched UO2 fuel elements clad in Zircaloy.4 alloy. This is done in collaboration with Reduced Enrichment for Research and Test Reactor. The versatile MCNP code was used to analy.e the neutronics parameters given in the SAR of HEU core, thereby.characterizing the core. Subsequently. the LEU core was indentified with necessary.changes to the HEU MCNP model. It was ascertained that the reactivity.for the LEU core with the same number of fuel pins as the HEU was inadequate, hence the fuel pins were increased from 344 to 348. The neutron flux at the irradiation sites was found to be below the nominal value at full power for the LEU and hence the nominal power was increased to 34 kW for a nominal flux value of 1 × 1012 n/cm2.s. The parameters investigated for the HEU and LEU are shown in this paper.

关键词： Neutronics Multiplication Factor Reactivity Neutron Flux

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MCNP Simulation of Phy.ics Parameters of Dispersion Fuels for Conversion of NIRR-1 to LEU

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World Journal of Nuclear Science and Technology 2018年第2期8卷 23-29页

作者： Kola Ibikunle Umar Sadiq y.kubu viva ibrahim Sunday.Adesunloy. Jonah Department of Phy.ics Ahmadu Bello University Zaria Nigeria Centre for Energy.Research and Training Ahmadu Bello University Zaria Nigeria

The Nigeria Research Reactor-1 (NIRR-1) is one of the Commercial Miniature Neutron Source Reactors (MNSRs) sited outside China and scheduled for conversion under the auspices of Reduced Enrichment for Research and Test Reactors (RERTR) program. Since 2006, the reduction in the fuel enrichment of MSNR facilities from greater than 90% HEU cores to less than 20% LEU cores has been embarked upon. Consequently.in this work, the phy.ics parameters of three dispersion LEU fuels, which include U3Si, U3Si2, and U9Mo enriched to 19.75% were determined by.the MCNP code to investigate their suitability.for the conversion of NIRR-1 to LEU. The following reactor core phy.ics parameters were computed for the LEU fuel options: clean cold core excess reactivity.(ρex), control rod (CR) worth, shut down margin (SDM), neutron flux distributions in the irradiation channels and kinetics data (i.e. effective delay.d neutron fraction, βeff?and prompt neutron lifetime, lf). Results are compared with experimental and calculated data of the current HEU core and indicate that it would be feasible to use any.of the LEU options for the conversion of commercial MNSR in general and NIRR-1 in particular from HEU to LEU.

关键词： Neutronics Data HEU to LEU Conversion MNS Reactors Dispersion Fuels MCNP

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An Investigation of the Impact of Installation of Cd-Lined Irradiation Channel in NIRR-1 on Core Phy.ics Data for ENAA

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World Journal of Nuclear Science and Technology 2014年第1期4卷 21-25页

作者： Sunday.Adesunloy. Jonah Ray.ond Limen Njinga y.kubu viva ibrahim Centre for Energy.Research and Training Ahmadu Bello University Zaria Nigeria Phy.ics Department Ibrahim Badamasi Babangida University Lapai Nigeria

Prior to the installation of the Cd-liner in one of the large outer irradiation channels of NIRR-1, a Monte Carlo simulation was performed using MCNP5 version 1.4 code. This was done to investigate the effect of installation of Cd-liner in either an inner or outer irradiation channel on reactor phy.ics parameters. Data obtained indicate that the core excess reactivity.in both inner and outer irradiations channels is reduced by.3.60 ± 0.07 mk and 0.64 ± 0.06 mk, respectively. Considering the fact that NIRR-1 has a cold core excess reactivity.of 3.77 mk, results obtained show that installation of the 1 mm thick Cd-sheet in one of the large outer irradiation channels would have no significant impact on the core phy.ics data. After installation of a 1 mm Cd sheath in a large outer irradiation channel, the neutron flux distribution and the stability.in the irradiation channels were monitored by.foil activation method. Results indicate that the uniformity.of neutron flux distribution in the irradiation channel is preserved and the neutron flux data were found to be comparable with the data obtained before the installation.

关键词： Monte Carlo Simulation Core Phy.ics Data Cd-Liner NIRR-1

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