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Relevant bibliographies by topics / Ghana Research Reactor-1

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Journal articles

Academic literature on the topic 'Ghana Research Reactor-1'

Author: Grafiati

Published: 4 June 2025

Last updated: 23 June 2025

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Journal articles on the topic "Ghana Research Reactor-1"

1

Della, R., E. Alhassan, N. A. Adoo, C. Y. Bansah, B. J. B. Nyarko, and E. H. K. Akaho. "Stability analysis of the Ghana Research Reactor-1 (GHARR-1)." Energy Conversion and Management 74 (October 2013): 587–93. http://dx.doi.org/10.1016/j.enconman.2013.03.039.

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2

DORDOH-GASU, PHILIP. "Ageing Management Activities at the Ghana Research Reactor-1 Facility." Arab Journal of Nuclear Sciences and Applications 56, no. 2 (2023): 68–74. http://dx.doi.org/10.21608/ajnsa.2022.171880.1661.

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3

Abrefah, R. G., S. A. Birikorang, B. J. B. Nyarko, J. J. Fletcher, and E. H. K. Akaho. "Design of serpentine cask for Ghana research reactor-1 spent nuclear fuel." Progress in Nuclear Energy 77 (November 2014): 84–91. http://dx.doi.org/10.1016/j.pnucene.2014.06.011.

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4

Amoah, Prince, Edward Shitsi, Emmanuel Ampomah-Amoako, and Henry Cecil Odoi. "Transient Studies on Low-Enriched-Uranium Core of Ghana Research Reactor–1 (GHARR-1)." Nuclear Technology 206, no. 10 (2020): 1615–24. http://dx.doi.org/10.1080/00295450.2020.1713681.

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5

Ampomah-Amoako, E., E. H. K. Akaho, S. Anim-Sampong, and B. J. B. Nyarko. "Transient analysis of Ghana Research Reactor-1 using PARET/ANL thermal–hydraulic code." Nuclear Engineering and Design 239, no. 11 (2009): 2479–83. http://dx.doi.org/10.1016/j.nucengdes.2009.06.016.

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6

Ameyaw, F., R. Abrefah, S. Yamoah, and S. Birikorang. "Analysis and Estimation of Core Damage Frequency of Flow Blockage and Loss of Coolant Accident: A Case Study of a 10 MW Water-Water Research Reactor-PSA Level 1." Science and Technology of Nuclear Installations 2021 (June 26, 2021): 1–17. http://dx.doi.org/10.1155/2021/9423176.

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Fault trees (FT) and event trees (ET) are widely used in industry to model and evaluate the reliability of safety systems. This work seeks to analyze and estimate the core damage frequency (CDF) due to flow blockage (FB) and loss of coolant accident (LOCA) due to large rupture of primary circuit pipe with respect to a specific 10 MW Water-Water Research Reactor in Ghana using the FT and ET technique. Using FT, the following reactor safety systems: reactor protection system, primary heat removal system, isolation of the reactor pool, emergency core cooling system (ECCS), natural circulation heat removal, and isolation of the containment were evaluated for their dependability. The probabilistic safety assessment (PSA) Level 1 was conducted using a commercial computational tool, system analysis program for practical coherent reliability assessment (SAPHIRE) 7.0. The frequency of an accident resulting in severe core damage for the internal initiating event was estimated to be 2.51e − 4/yr for the large LOCA as well as 1.45e − 4/yr for FB, culminating in a total core damage frequency of 3.96e − 4/yr. The estimated values for the frequencies of core damage were within the expected margins of 1.0e − 5/yr to 1.0e − 4/yr and of identical sequence of the extent as found for similar reactors.

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7

Boffie, J., H. C. Odoi, E. H. K. Akaho, B. J. B. Nyarko, and K. Tuffour-Achampong. "Design of an additional safety rod for Ghana Research Reactor-1 using MCNP5 code." Nuclear Engineering and Design 245 (April 2012): 13–18. http://dx.doi.org/10.1016/j.nucengdes.2011.12.030.

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8

Amponsah-Abu, E. O., J. K. Gbadago, E. H. K. Akaho, et al. "Assessment of the reliability of neutronic parameters of Ghana Research Reactor-1 control systems." Nuclear Engineering and Design 281 (January 2015): 72–78. http://dx.doi.org/10.1016/j.nucengdes.2014.11.018.

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9

Obeng, Henry K., Sylvester A. Birikorang, Kwame Gyamfi, Simon Adu, and Andrew Nyamful. "Assessment of radiological consequence of a hypothetical accident at the Ghana Research Reactor-1 facility based on terrorist attack." Science Progress 104, no. 4 (2021): 003685042110549. http://dx.doi.org/10.1177/00368504211054986.

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The International Atomic Energy Agency defines a nuclear and radiation accident as an occurrence that leads to the release of radiation causing significant consequences to people, the environment, or the facility. During such an event involving a nuclear reactor, the reactor core is a critical component which when damaged, will lead to the release of significant amounts of radionuclides. Assessment of the radiation effect that emanates from reactor accidents is very paramount when it comes to the safety of people and the environment; whether or not the released radiation causes an exposure rate above the recommended threshold nuclear reactor safety. During safety analysis in the nuclear industry, radiological accident analyses are usually carried out based on hypothetical scenarios. Such assessments mostly define the effect associated with the accident and when and how to apply the appropriate safety measures. In this study, a typical radiological assessment was carried out on the Ghana Research Reactor-1. The study considered the available reactor core inventory, released radionuclides, radiation doses and detailed process of achieving all the aforementioned parameters. Oak Ridge isotope generation-2 was used for core inventory calculations and Hotspot 3.01 was also used to model radionuclides dispersion trajectory and calculate the released doses. Some of the radionuclides that were considered include I-131, Sr-90, Cs-137, and Xe-137. Total effective doses equivalent to released radionuclides, the ground deposition activity and the respiratory time-integrated air concentration were estimated. The maximum total effective doses equivalent value of 5.6 × 10−9 Sv was estimated to occur at 0.1 km from the point of release. The maximum ground deposition activity was estimated to be 2.5 × 10−3 kBq/m3 at a distance of 0.1 km from the release point. All the estimated values were found to be far below the annual regulatory limits of 1 mSv for the general public as stated in IAEA BSS GSR part 3.

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10

Muswema, J. L., E. O. Darko, J. K. Gbadago, and E. K. Boafo. "Atmospheric dispersion modeling and radiological safety analysis for a hypothetical accident of Ghana Research Reactor-1 (GHARR-1)." Annals of Nuclear Energy 68 (June 2014): 239–46. http://dx.doi.org/10.1016/j.anucene.2014.01.029.

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