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

DOI: 10.4236/wjnst.2024.141003, PP. 72-85

Keywords: GHARR-1, Power Peaking Factor, Nuclear Reactor Safety, Low Enriched Uranium Core, Operational Longevity, Thermal Hydraulics

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Abstract:

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.

References

[1]  Zamani, P., Foomezhi, A. and Ghorbani Nohooji, S. (2021) A Review of Medium Voltage Single-Core Cable Armouring, Induced Currents and Losses. Energy and Power Engineering, 13, 272-292.
https://doi.org/10.4236/epe.2021.137019
[2]  Ernawati, T., Anggraeni, M.K., Hendrawan, K.A., Pratiwi, R.W., Ernawati, T., Anggraeni, M.K., Hendrawan, K.A. and Pratiwi, R.W. (2020) Distribution of Axial Length, Anterior Chamber Depth and Lens Thickness of Pre-Operative Cataract Patients in Indonesian Population. The Open Ophthalmology Journal, 10, 288-296.
https://doi.org/10.4236/ojoph.2020.104032
[3]  Amponsah-Abu, E.O., Nyarko, B.J.B. and Edziah, R. (2019) Design and Construction of Pneumatic Transfer System Controller Unit for Ghana MNSR. Journal of Control Science and Engineering, 2019, Article ID: 6450987.
https://doi.org/10.1155/2019/6450987
[4]  Abrefah, R.G., Birikorang, S.A., Nyarko, B.J.B., Fletcher, J.J. and Akaho, E.H.K. (2014) Design of Serpentine Cask for Ghana Research Reactor-1 Spent Nuclear Fuel. Progress in Nuclear Energy, 77, 84-91.
https://doi.org/10.1016/j.pnucene.2014.06.011
[5]  Bae, I.H., Na, M.G., Lee, Y.J. and Park, G.C. (2008) Calculation of the Power Peaking Factor in a Nuclear Reactor Using Support Vector Regression Models. Annals of Nuclear Energy, 35, 2200-2205.
https://doi.org/10.1016/J.ANUCENE.2008.09.004
[6]  Mohd Ali, N.S., Hamzah, K., Idris, F., Basri, N.A., Sarkawi, M.S., Sazali, M.A., Rabir, H., Minhat, M.S. and Zainal, J. (2022) Power Peaking Factor Prediction Using ANFIS Method. Nuclear Engineering and Technology, 54, 608-616.
https://doi.org/10.1016/j.net.2021.08.011
[7]  Odoi, H.C., Abrefah, R.G., Aboh, I.J.K., Gbadago, J.K., Birikorang, S.A. and Amponsh-Abu, E.O. (2014) Study of Criticality Safety and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LEU Core Using MCNP Code. World Journal of Nuclear Science and Technology, 4, 46-52.
https://doi.org/10.4236/wjnst.2014.41008
[8]  Agyekum, E.B., Ansah, M.N.S. and Afornu, K.B. (2020) Nuclear Energy for Sustainable Development: SWOT Analysis on Ghana’s Nuclear Agenda. Energy Reports, 6, 107-115.
https://doi.org/10.1016/j.egyr.2019.11.163
[9]  Mweetwa, B.M., Ampomah-Amoako, E., Akaho, E.H.K. and Odoi, C. (2018) Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code. World Journal of Nuclear Science and Technology, 8, 160-175.
https://doi.org/10.4236/wjnst.2018.84014
[10]  Abrefah, R.G. and Ned, S.I.G. (2018) Estimation of the Dose Rate of Nuclear Fuel of Ghana Research Reactor-1 (GHARR-1) Using ORIGEN-S and MCNP 6. Progress in Nuclear Energ, 105, 309-317.
https://doi.org/10.1016/j.pnucene.2018.02.002
[11]  Amin, E.A., Bashter, I.I., Hassan, N.M. and Mustafa, S.S. (2017) Fuel Burnup Analysis for IRIS Reactor Using MCNPX and WIMS-D5 Codes. Radiation Physics and Chemistry, 131, 73-78.
https://doi.org/10.1016/j.radphyschem.2016.10.019
[12]  Didi, A., Dadouch, A., Bencheikh, M. and Jai, O. (2017) Monte Carlo Simulation of Thermal Neutron Flux of Americium-Beryllium Source Used in Neutron Activation Analysis. Moscow University Physics Bulletin, 72, 460-464.
https://doi.org/10.3103/S0027134917050022
[13]  Mweetwa, B.M., Ampomah-Amoako, E. and Akaho, E.H.K. (2017) Transient Studies of Ghana Research Reactor-1 after Nineteen (19) Years of Operation Using PARET/ANL Code. World Journal of Nuclear Science and Technology, 7, 223-231.
https://doi.org/10.4236/wjnst.2017.74018
[14]  IAEA (2000) IAEA Safety Standards Series: Safety of Nuclear Power Plants. 323-346.
[15]  Amoah, P., Shitsi, E., Ampomah-Amoako, E. and Odoi, H.C. (2020) Transient Studies on Low-Enriched-Uranium Core of Ghana Research Reactor-1 (GHARR-1). Nuclear Technology, 206, 1615-1624.
https://doi.org/10.1080/00295450.2020.1713681
[16]  Amatullah, A., Agung, A. and Arif, A. (2021) Minimizing Power Peaking Factor of BEAVRS-Based Reactor Using Polar Bear Optimization Algorithms. IOP Conference Series: Earth and Environmental Science, 927, Article ID: 012004.
https://doi.org/10.1088/1755-1315/927/1/012004
[17]  Bae, I.H., Na, M.G., Lee, Y.J. and Park, G.C. (2009) Estimation of the Power Peaking Factor in a Nuclear Reactor Using Support Vector Machines and Uncertainty Analysis. Nuclear Engineering and Technology, 41, 1181-1190.
https://doi.org/10.5516/NET.2009.41.9.1181
[18]  Keiser, D.D. (2012) 3.15-Metal Fuel-Cladding Interaction. Comprehensive Nuclear Materials, 3, 423-441.
https://doi.org/10.1016/B978-0-08-056033-5.00067-7
[19]  Thakur, A., Singh, B. and Krishnani, P.D. (2013) In-Core Fuel Management for AHWR. Annals of Nuclear Energy, 57, 47-58.
https://doi.org/10.1016/j.anucene.2013.01.034
[20]  Torabi, M., Lashkari, A., Masoudi, S.F. and Bagheri, S. (2018) Neutronic Analysis of Control Rod Effect on Safety Parameters in Tehran Research Reactor. Nuclear Engineering and Technology, 50, 1017-1023.
https://doi.org/10.1016/j.net.2018.05.008
[21]  Mustafa, S.S. (2021) The Effect of Control Rods on The Reactivity and Flux Distribution of BWR 4 Bundle Using MCNPX Code. Scientific Reports 2021, 11, 1-17.
https://doi.org/10.1038/s41598-021-88067-0
[22]  Akaho, E.H.K., Anim-Sampong, S., Maakuu, B.T., Dodoo-Amoo, D.N.A. (2000) Dynamic Feedback Characteristics of Ghana Research Reactor-1. Journal of the Ghana Science Association, 2, 200-208.
https://doi.org/10.4314/JGSA.V2I3.17896
[23]  Sarker, I.H. (2021) Machine Learning: Algorithms, Real-World Applications and Research Directions. SN Computer Science, 2, Article No. 160.
https://doi.org/10.1007/s42979-021-00592-x
[24]  Park, J., Khassenov, A., Kim, W., Choi, S. and Lee, D. (2019) Comparative Analysis of VERA Depletion Benchmark through Consistent Code-To-Code Comparison. Annals of Nuclear Energy, 124, 385-398.
https://doi.org/10.1016/j.anucene.2018.10.024

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