Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes

Amin, E.; Bashter, I.I.; Hassan, Nabil M.; Mustafa, Sayed Saeed

doi:10.1016/j.radphyschem.2016.10.019

Cited by 8 publications

(2 citation statements)

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“…The idea of coupling MCNP5 with Monteburns in reference 1 depends on calculating the concentrations of fuel isotopes at the required irradiation value of the full core. Then the new atom densities are transferred to MCNP5 file to calculate the desired parameters as k-eff and power distribution at the stage under study 18 . The uranium enrichment, the boron enrichment in the control blade and the volume of moderator in the reactor core are important factors which play an important role in determining the k-eff value and the flux distribution shape 19 .…”

Section: Resultsmentioning

confidence: 99%

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Mustafa

2021

Sci Rep

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This paper has three main objectives related to the neutronic and burnup analysis of the BWR (Boiling Water Reactor) Four-Lattice. The first objective is to provide partial validation of the MCNPX code for this lattice by comparing its results with Scale-5.1 results. Validation of the MCNPX to calculate effective multiplication factor and reactivity rod worth for the F-Lattice is provided. This is carried out in case of instantly removing the control blade and replacing it with a graphite moderator. Moreover, spatial neutron flux distributions using F-mesh card over the bundle and the control blade are investigated at inserting and withdrawing the B4C. The second objective is to perform parametric design studies of the F-Lattice. Areas of particular interest are the effect of increased or decreased blade width on the neutron flux throughout the bundle. It is found that the presence of carbon in the control blade at withdrawing the B4C makes the reactor supercritical, (K-eff = 1.22206). On the other hand, the use of B4C blade presents (K-eff = 0.93521). Consequently, the reactivity of 10% B4C thinner case is higher that of 10% B4C thicker. The simulation also showed that the B4C blade had an effective role in decreasing the thermal flux at the periphery of the bundle. This is contrast to the effect of carbon that moderates fast to thermal neutrons. The third part of this work aims at studying the burnup calculations using MCNPX code for 30 days burn with 1 day time step then for 20 months burn with 2 week time steps for the lattice. At the end of the work, it is very important to determine the most proper bundle model that achieves a prolonged fuel burn and flatting thermal flux distribution. For reaching this goal, three cases (B4C, 10% thinner of B4C and 10% thicker) are simulated by MCNPX code till 70 GWd/ton. It is found that the B4C and 10% thicker are the appropriate models that can satisfy the safety considerations of the Compact Modular Boiling Water Reactor.

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Section: Resultsmentioning

confidence: 99%

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Mustafa

2021

Sci Rep

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“…• The reactor core was segmented into a maximum of 21 axial sections based on the hottest and coldest fuel pins. This initial segmentation, conducted using the MCNPX code, establishes the framework for a detailed power distribution analysis [11].…”

Section: Segmentation and Initial Analysis With Mcnpx Codementioning

confidence: 99%

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

Ahiave,

Ampomah-Amoako,

Abrefah

et al. 2024

WJNST

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This study aims to thoroughly investigate the axial power peaking factors (PPF) within the low-enriched uranium (LEU) core of the Ghana Research Reactor-1 (GHARR-1). This study uses advanced simulation tools, like the MCNPX code for analysing neutron behavior and the PARET/ANL code for understanding power variations, to get a clearer picture of the reactor's performance. The analysis covers the initial six years of GHARR-1's operation and includes projections for its whole 60-year lifespan. We closely observed the patterns of both the highest and average PPFs at 21 axial nodes, with measurements taken every ten years. The findings of this study reveal important patterns in power distribution within the core, which are essential for improving the safety regulations and fuel management techniques of the reactor. We provide a meticulous approach, extensive data, and an analysis of the findings, highlighting the significance of continuous monitoring and analysis for proactive management of nuclear reactors. The findings of this study not only enhance our comprehension of nuclear reactor safety but also carry significant ramifications for sustainable energy progress in Ghana and the wider global context. Nuclear engineering is essential in tackling global concerns, such as the demand for clean and dependable energy sources. Research on optimising nuclear reactors, particularly in terms of safety and efficiency, is crucial for the ongoing advancement and acceptance of nuclear energy.

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Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor

Al‐Qahtani

Buijs

Day

2020

Annals of Nuclear Energy

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Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes

Cited by 8 publications

References 0 publications

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis

Serpent-2 and OSCAR-4 computational tools compared against McMaster nuclear reactor improved operational data history for U-235 fuel inventory tracking, local power tracking and validation of multiplication factor

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