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

Author: Grafiati

Published: 4 June 2025

Last updated: 23 June 2025

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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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11

Amponsah-Abu, E. O., B. J. B. Nyarko, and R. Edziah. "Design and Construction of Pneumatic Transfer System Controller Unit for Ghana MNSR." Journal of Control Science and Engineering 2019 (August 1, 2019): 1–15. http://dx.doi.org/10.1155/2019/6450987.

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Pneumatic Transfer System (PTS) is an auxiliary system of Ghana Research Reactor-1 (GHARR-1) used to transfer sample capsule in and out of the reactor irradiation sites. The PTS’ controller unit design and construction were carried out because the original transfer system was not designed to operate in cyclic NAA. To address these situations, a Programmable Logic Controller (PLC) has been used to design and construct a control unit to facilitate a cyclic neutron activation analysis (CNAA) application for GHARR-1. The design has been simulated successfully using a LOGO Soft Comfort software, version 8. The constructed control unit has been tested experimentally using 220 AC volts electric bulbs to represent solenoid valves. The results show that the sample-IN and sample-OUT bulbs come ON and go OFF to represent the solenoid valves opening and closing for sample transfer. The study has shown that the computer based PLC controller unit for PTS is capable of facilitating both cyclic and conventional NAA application for the GHARR-1.

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12

Mweetwa, Bright Madinka, Emmanuel Ampomah-Amoako, and Edward Horga Korbla Akaho. "Transient Studies of Ghana Research Reactor-1 after Nineteen (19) Years of Operation Using PARET/ANL Code." World Journal of Nuclear Science and Technology 07, no. 04 (2017): 223–31. http://dx.doi.org/10.4236/wjnst.2017.74018.

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13

Abrefah, R. G., and P. A. A. Essel. "Estimation of Decay Heat in Ghana Research Reactor-1 Auxiliary Components Using ORIGEN-S: A Case Study." Nuclear Technology 205, no. 9 (2019): 1245–50. http://dx.doi.org/10.1080/00295450.2019.1585736.

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14

Birikorang, S. A., R. G. Abrefah, R. B. M. Sogbadji, B. J. B. Nyarko, J. J. Fletcher, and E. H. K. Akaho. "Ground deposition assessment of radionuclides following a hypothetical release from Ghana Research Reactor-1 (GHARR-1) using atmospheric dispersion model." Progress in Nuclear Energy 79 (March 2015): 96–103. http://dx.doi.org/10.1016/j.pnucene.2014.11.013.

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15

Abrefah, R. G., P. A. A. Essel, and H. C. Odoi. "Estimation of the dose rate of nuclear fuel of Ghana Research Reactor-1 (GHARR-1) using ORIGEN-S and MCNP 6." Progress in Nuclear Energy 105 (May 2018): 309–17. http://dx.doi.org/10.1016/j.pnucene.2018.02.002.

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16

Alhassan, S., S. V. Beliavskii, and V. N. Nesterov. "Investigative study of the radiation damage on fuel clad of miniature neutron source reactor using computational tools." Journal of Physics: Conference Series 2064, no. 1 (2021): 012103. http://dx.doi.org/10.1088/1742-6596/2064/1/012103.

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Abstract Core conversion requires some evaluation of the reactor safety. Changes to the reactivity worth, shutdown margin, power density and material properties are crucial to the proper functioning of the reactor. The focus of this article is to study the neutron flux distribution in the reactor core and radiation damage on candidate clads. The Ghana Research Reactor-1 (GHARR-1) operates at maximum power of 30 kW in order to attain a flux of 1.0× 1012 n·cm–2·s for the high enriched uranium core. Using the GHARR-1 core geometry, considering 348 fuel pins, the multiplication factor (Keff) is calculated at enrichments of 10%, 12.5%, 16%, 20%, 30% and 90.2%. The spectrum of neutron flux generated in the 26 group is also calculated at the specified enrichments. The ion/particle interactions with the targets (clad) were studied in the Stopping and Range of Ion in Matter code to establish the best clad material based on recorded defects and vacancies generated. From the calculations and simulations, the best choice from the candidate clads based on the assessment is SiC. The calculation of the fuel campaign length gives 7.5 years. The defects sustained by the prospective clad showed low susceptibility to swelling and other forms of deformation.

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17

Abrefah, R. G., S. Anim-Sampong, B. J. B. Nyarko, E. H. K. Akaho, and R. B. M. Sogbadji. "Measurement of neutron flux distribution in the irradiation channel in the Ghana Research Reactor-1 using Monte Carlo method." Progress in Nuclear Energy 53, no. 2 (2011): 189–94. http://dx.doi.org/10.1016/j.pnucene.2010.07.002.

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18

Abrefah, R. G., R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, and B. J. B. Nyarko. "Design of epicadmium-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP." Nuclear Engineering and Design 240, no. 4 (2010): 744–46. http://dx.doi.org/10.1016/j.nucengdes.2009.12.016.

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19

Abrefah, R. G., R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, and B. J. B. Nyarko. "Comparison of the effects of cadmium-shielded and boron carbide-shielded irradiation channel of the Ghana Research Reactor-1." Nuclear Engineering and Design 241, no. 8 (2011): 3017–20. http://dx.doi.org/10.1016/j.nucengdes.2010.05.005.

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20

Ameyaw, Felix, Akwasi Ayensu, and E. H. K. Akaho. "Modeling and simulation of coupled nuclear heat energy deposition and transfer in the fuel assembly of the Ghana Research Reactor-1 (GHARR-1)." Nuclear Engineering and Design 241, no. 12 (2011): 5183–88. http://dx.doi.org/10.1016/j.nucengdes.2011.09.013.

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21

Abrefah, R. G., R. B. M. Sogbadji, E. Ampomah-Amoako, S. A. Birikorang, H. C. Odoi, and B. J. B. Nyarko. "Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP." Applied Radiation and Isotopes 69, no. 1 (2011): 85–89. http://dx.doi.org/10.1016/j.apradiso.2010.06.024.

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22

Odoi, Henry Cecil, Edward H. K. Akaho, Sunday A. Jonah, Rex Gyeabour Abrefah, and Viva Y. Ibrahim. "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 04, no. 01 (2014): 46–52. http://dx.doi.org/10.4236/wjnst.2014.41008.

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23

Mweetwa, Bright Madinka, Emmanuel Ampomah-Amoako, Edward Horga Kordzo Akaho, and Cecil Odoi. "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 08, no. 04 (2018): 160–75. http://dx.doi.org/10.4236/wjnst.2018.84014.

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24

Abrefah, R. G., B. J. B. Nyarko, E. H. K. Akaho, S. Anim Sampong, and R. B. M. Sogbadji. "Axial and radial distribution of thermal and epithermal neutron fluxes in irradiation channels of the Ghana Research Reactor-1 using foil activation analysis." Annals of Nuclear Energy 37, no. 8 (2010): 1027–35. http://dx.doi.org/10.1016/j.anucene.2010.04.017.

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25

Boffie, J., E. H. K. Akaho, B. J. B. Nyarko, H. C. Odoi, K. Tuffour-Achampong, and R. G. Abrefah. "Investigative studies on the effects of cadmium rabbits on high enriched uranium-fueled and low enriched uranium-fueled cores of Ghana Research Reactor-1 using MCNP5 code." Nuclear Engineering and Design 265 (December 2013): 514–18. http://dx.doi.org/10.1016/j.nucengdes.2013.07.017.

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26

Shitsi, Edward, Prince Amoah, Emmanuel Ampomah-Amoako, and Henry Cecil Odoi. "Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core." Journal of Thermal Science and Engineering Applications 12, no. 5 (2020). http://dx.doi.org/10.1115/1.4046598.

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Abstract Research reactors all over the world are expected to operate within certain safety margins just like pressurized water reactors and boiling water reactors. These safety margins mainly include onset of nucleate boiling ratio (ONBR), departure from nucleate boiling ratio (DNBR), and flow instability ratio (FIR) in addition to the maximum clad or fuel temperature and saturation temperature or boing point of the coolant inside the core of the reactor. This study carried out steady-state safety analysis of the Ghana Research Reactor-1 (GHARR-1) with low enriched uranium (LEU) core. Monte Carlo N-particle (MCNP) code was used to obtain radial and axial power peaking factors used as inputs in the preparation of the input file of plate temperature code of Argonne National Laboratory (PLTEMP/ANL code), which was then used to obtain the mentioned safety parameters of GHARR-1 with LEU core in this study. The data obtained on the ONBR were used to obtain the initiation of nucleate boiling boundary data with respect to the active length of the reactor core for various reactor powers. The obtained results for LEU core were also compared with that of the high enriched uranium (HEU) core. The results obtained show that the 34 kW GHARR-1 with LEU core is safe to operate just as the previous 30 kW HEU core was safe to operate.

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27

Akaho, E. H. K., S. Anim-Sampong, B. T. Maakuu, and D. N. A. Dodoo-Amoo. "Dynamic feedback characteristics of Ghana Research Reactor-1." Journal of the Ghana Science Association 2, no. 3 (2000). http://dx.doi.org/10.4314/jgsa.v2i3.17896.

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28

Gyamfi, Kwame, Philip Owusu-Manteaw, Edward Shitsi, and Edith Amoakie Amoatey. "Assessment of Occupational Radiation Exposures at Ghana Research Reactor-1 Facility." NEW SOLUTIONS: A Journal of Environmental and Occupational Health Policy, June 7, 2024. http://dx.doi.org/10.1177/10482911241259515.

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The annual occupational doses for workers at the Ghana Research Reactor-1 facility were assessed for the period 2018–2021. The dose records of monitored staff were retrieved and analysis done for dose distribution and collective effective doses. Thermoluminiscent dosimeters were used to monitor the occupational exposures. The dosimeters were evaluated for the cumulative radiation dose levels using the Harshaw 6600 TLD reader system. Annual dose of 1.52 mSv/year was the maximum acquired by an individual. An annual average effective dose range of 0.20–1.36 mSv was determined for all workers. The annual total collective effective dose was established to be in the range of 0.40–10.08 man-Sv. The 20 mSv annual limit for occupational exposure was not exceeded for monitored workers. The assessment shows that the GHARR-1 facility, in terms of radiation health effects, is a favorable environment for workers since exposures are mostly below occupational exposure limit.

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29

Ampomah-Amoako, Emmanuel, Benjamin J. B. Nyarko, Edward H. K. Akaho, Rex G. Abrefah, Ekua Mensimah, and Kwaku A. Danso. "Operational Safety Experience of Ghana Research Reactor-1 and Its Impact on the Nuclear Power Program in Ghana." Environmental Research, Engineering and Management 56, no. 2 (2011). http://dx.doi.org/10.5755/j01.erem.56.2.271.

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30

Ameyaw, Felix, R. G. Abrefah, and E. O Amponsah-Abu. "A Review of Ghana Research Reactor-1 (GHARR-1) Component Aging Degradation Problems and Ways of Mitigation." Environmental Research, Engineering and Management 74, no. 3 (2018). http://dx.doi.org/10.5755/j01.erem.74.3.19974.

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31

Nzoley, Charles, Emmanuel K. Boafo, Basma Foad, and H. C. Odoi. "Development of a Neutronics–Thermal-Hydraulic Coupling Methodology to Support the Safety Analysis of Ghana Research Reactor-1." Nuclear Technology, May 28, 2025, 1–33. https://doi.org/10.1080/00295450.2025.2475543.

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32

E.O., Amponsah-Abu, Nyarko B.J.B., and Edziah R. "Programmable Logic Controller based mitigation of obsolescence control unit of GHARR-1 Pneumatic Transfer System." August 22, 2019. https://doi.org/10.5281/zenodo.3374910.

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Ghana Research Reactor-1 (GHARR-1) is a Miniature Neutron Source Reactor (MNSR) used mainly for Neutron Activation Analysis (NAA), Education and Training. GHARR-1 uses an auxiliary Pneumatic Transfer System (PTS) for the transfer of sample capsules in and out of the irradiation sites. The 90.2 % highly enriched uranium (HEU) core of GHARR-1 was recently converted to a 13 % low enriched uranium (LEU) core. The conversion resulted in the thermal power of GHARR-1 increased from 30 kW to 34 kW whiles maintaining the neutron flux at 1 x 10<sup>12 </sup>n/cm<sup>2</sup>s. Most of the components used to design the existing one-short conventional NAA controller unit are outmoded and out of stock in the local Ghanaian market, posing threat to future maintenance. To address this situation, a Programmable Logic Controller (PLC) has been used to design a control unit to facilitate the NAA application. This paper outlines the design of a stable +12 /+24 VDC voltage regulated power supply to operate the PLC and control an 8-way solid state relay bank. The relay bank was designed to operate the solenoid valves that open and close a compressed-air to transfer samples into the reactor for irradiation. Function block diagram programming language was used for the design of the PTS controller unit. The paper highlights the simulation results in which electric bulbs were used to represent the solenoid valves to achieve the opening and closing mechanism for the transfer of samples.  Implementation of the results obtained from the study would eliminate the difficulty of getting up-to-date components to replace the outmoded ones in the PTS controller.

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33

Vowotor, Michael Kwame, Raymond Edziah, Samuel Sonko Sackey, Emmanuel Kofi Amewode, and Sandra Baaba Frempong. "Assessment of Arsenic and Copper Pollution of the Benya Lagoon, Ghana By Neutron Activation Analysis." Journal of Engineering Advancements, December 15, 2021, 180–87. http://dx.doi.org/10.38032/jea.2021.04.004.

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Heavy metal concentrations in some water bodies and the soil beneath these waters. These would have detrimental consequences on these water users and consumers of the fish in that water. Instrumental Neutron Activation Analysis technique using the Ghana Research Reactor-1 was employed to find out the concentrations of two heavy metals, Arsenic (As) and Copper (Cu) in the sediments, fishes, and water collected from the Benya Lagoon in the KEEA, Ghana. Cumulatively, Copper was found to be greater in concentration than Arsenic concerning the three parts of the ecology under study. On the other hand, Arsenic was more concentrated in the sediments than Copper, and Copper was more concentrated in the water and fish than Arsenic. Cumulatively, the level of contamination of Arsenic and Copper decreased in the order fish > sediment > water. Though Arsenic and Copper were found in elevated amounts in both water and fish which rendered the Lagoon water unsuitable for human use and the fish from the Lagoon unsafe for consumption, their concentrations in the sediment were found to have a low ecological risk index on the environment.

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34

Asare, Ebenezer, Charles Klutse, and Francis Acquaye. "Validation of k0-Standardization Procedure of Instrumental Neutron Activation Analysis at Ghana Research Reactor-1 Facility for the Determination of Rare Earth Elements." Arab Journal of Nuclear Sciences and Applications, February 1, 2022, 1–15. http://dx.doi.org/10.21608/ajnsa.2021.91014.1504.

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35

BIRIKORANG, Sylvester Attakorah, R. G. Abrefah, and H. K. Obeng. "Radiological Dose Assessment for the Ghana Research Reactor-1 at Shutdown Using Dispersion Model: Conversion from High-Enriched Uranium to Low-Enriched Uranium Fuel." Environmental Research, Engineering and Management 74, no. 1 (2018). http://dx.doi.org/10.5755/j01.erem.74.1.19948.

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36

Asante-Poku, Adwoa, Kwame G. Aning, Bashiru Boi-Kikimoto, and Dorothy Yeboah-Manu. "Prevalence of bovine tuberculosis in a dairy cattle farm and a research farm in Ghana." Onderstepoort J Vet Res 81, no. 2 (2014). http://dx.doi.org/10.4102/ojvr.v81i2.716.

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The aim of the study was to estimate the prevalence of bovine tuberculosis (BTB) and to identify the mycobacterial species causing BTB in a dairy farm and research farm. Six hundred and eighty-five cattle were screened for BTB by using the Comparative intradermal tuberculin test (CTT). Positive reactors were slaughtered and carcasses were taken for isolation of mycobacterial species. This was followed by speciation of isolates using both standard conventional and molecular assays. Seventeen of the cattle were positive by CTT, giving a crude BTB prevalence of 2.48% among cattle from the two farms. Six of the 17 samples (35.30%) yielded positive acid-fast bacilli cultures and three of the isolates were identified as Mycobacterium tuberculosis complex (MTBC), which were sub-divided into two Mycobacterium tuberculosis sensu scrito (Mtb) and one Mycobacterium africanum; the remaining three were Mycobacterium other than tuberculoisis (MOTT). Spoligotyping further characterised the two Mtb isolates as Ghana (spoligotype Data Base 4 number 53) and Latin American Mediterranean (LAM), whilst spoligotyping and Single Nucleotide Polymorphism (SNP) analysis typed the M. africanum as West African 1. Microseq 500 analysis identified two of the MOTT as Mycobacterium flavescens and Mycobacterium Moriokaense respectively, whilst the remaining one could not be identified. This study observed the prevalence of bovine TB among cattle from two farms in Ghana as 2.48% and confirms the public health importance of M. africanum as a pathogen in Ghana.

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