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5 articles for “Axial fuel”
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Design Boiling Water Reactor Core Model Using MCNPX for Studying the Burnable Poisons and the Axial Enrichment Fuel Effect on the Neutronic Characteristics
Abstract: The incorporation of gadolinium directly into nuclear fuel is important for improving the reactor behavior and satisfying the safety criteria during the core lifetime. MCNPX (Monte Carlo N–Particle code extended) has been used for designing Advanced Boiling Water Reactor model. MCNPX code based on Monte Carlo method, is used to design a three-dimensional model for a BWR fuel assembly in a typical operating temperature and pressure conditions. This model has …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 1, 2013 · pp. 21–35 Read article
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Study the Effect of Gd2O3 on the Neutronic Characteristics of Boiling Water Reactor using MCNPX Code
Abstract: MCNPX code (Monte Carlo N–Particle code extended) is used to design Boiling Water Reactor (BWR) bundle model. This model is designed to study the effect of Gd2O3 on the reactivity effect of voiding, void coefficient, neutron flux and normalized power. The incorporation of Gd2O3 directly into the UO2 fuel is the most attractive process, because of its significant effect on the fuel life in the core of the reactor. The …
Published in Journal of Nuclear Engineering & Technology · Vol. 5, Issue 3, 2015 · pp. 26–32 Read article
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Thermal-hydraulic Safety Assessment of a Miniature Neutron Source Reactor
Abstract: The main objective of this study is to assess the thermal-hydraulic safety capability of the PLTEMP/ANL v 4.0 in analyzing Ghana Research Reactor-1 (GHARR-1), with vertical fuel rods cooled by natural convection, operating at a nominal power (30 kW) with sufficient safety margins. The neutronic analysis of the core was performed using MCNP X code, where parameters of interest were the power distributions and the power peaking factors. The thermal-hydraulic …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 3, 2013 · pp. 18–44 Read article
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Development of a Steady State Temperature Distribution Code (STD 1.0) for Predicting Thermal-Hydraulics Parameters of MNSR
Abstract: A steady-state temperature distribution code has been developed using Visual Basic 6.0 programming language for the estimation of steady-state temperature distribution in an averaged fuel element of Miniature Neutron Source Reactor. The STD 1.0 code is composed of three parts: Main Menu Window which shows the title of the code, picture of the Nigeria Research Reactor-1 in operation and the link to the other two windows; Radial Temperature Distribution Window, …
Published in Journal of Nuclear Engineering & Technology · Vol. 3, Issue 2, 2013 · pp. 1–13 Read article
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Numerical Simulation of Air Flow Field of A Gas Turbine Engine Air blast Atomizer
Abstract: One of the most crucial process that occurs before the fuel is burned in the combustion chamber is atomization. The performance of a engine will be depend mainly on the fuel mixture. Performance of the engine depends on atomization process because it breaks the bulk fuel into small droplets and injects it into the combustion chamber, in order to make this happen consequently the dimensions of most of the fuel …
Published in Journal of Polymer & Composites · Vol. 11, Issue 13, 2023 · pp. 169–180 Read article