Radiological Dose Assessment for the Ghana Research Reactor-1 at Shutdown Using Dispersion Model: Conversion from High-Enriched Uranium to Low-Enriched Uranium Fuel

Birikorang, S.A.; Abrefah, R.G.; Obeng, H. K.

doi:10.5755/j01.erem.74.1.19948

Cited by 3 publications

(5 citation statements)

References 4 publications

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“…These results indicate that no worse initiating accident with this type of LEU reactor core will have a threat to human activities within and beyond its physical borders. In comparison with earlier studies, 21,22,23 it can be seen that the above-estimated radionuclides and their respective doses for the postulated design basis accident and atmospheric transport calculation remain within and far below the acceptable regulatory limits of 1 mSv per year. The results were in good agreement with other researchers.…”

Section: Tede Results and Analysismentioning

confidence: 52%

Assessment of radiological consequence of a hypothetical accident at the Ghana Research Reactor-1 facility based on terrorist attack

et al. 2021

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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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Section: Tede Results and Analysismentioning

confidence: 52%

Assessment of radiological consequence of a hypothetical accident at the Ghana Research Reactor-1 facility based on terrorist attack

et al. 2021

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“…The calculation only the fission products of Iodine radioisotope 131 I, 137 Cs, and 90 Sr. These nuclides were selected based on their physical and chemical properties, volatility, and their contribution to collective dose, particularly in the thyroid gland [24]. The calculation considers release fractions indicated in the US-NRC regulatory guide 1.183 and described in WASH-1400 (NUREG-75/014) document [25][26].…”

Section: Materials and Methods 1) Site Description And Meteorological...mentioning

confidence: 99%

Numerical Dose Assessment and Short-term Radioactivity Impact on Foodstuff for Continuous Release from of TRIGA Mark II Research Reactor

Dahia,

Dadda,

Lyria Cheridi Deghal

et al. 2024

App. Envi. Res.

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This work is a contribution to the assessment of the radiological consequences of radioactivity and radiation dose for TRIGA Mark II research reactor during continuous operation. The potential release to the atmosphere of 131I, 137Cs, and 90Sr are computed in the South direction is calculated using CROM software. We have attempted to evaluate the daily concentration of radioactivity and its impact on foodstuff. The annual average dose received from internal and external irradiation by age group through the different pathways were also considered. The simulation results showed that the highest air concentration was found at 225 m distance from the source and the calculated doses were found to be significantly very low. The contribution of Iodine 131I is significantly higher in fruit vegetables, while the 137Cs and 90Sr are dominant in animal products. Furthermore, inhalation and ingestion of contaminated food were found to be the most likely routes of entry into the human body.

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“…Fig. 1 -General Methodology calculation by HotSpot code 6,7 resuspension, and ground shine) resulting from the release of radionuclides during the accident. 12 The external exposure is determined by the radiation emitted by the radionuclides and absorbed by the body, and the internal exposure is the result of the incorporation of deposit material into the human body by inhalation or ingestion.…”

Section: Site Specific Meteorological Conditionsmentioning

confidence: 99%

“…5 This mixture was based on physical and chemical properties of nuclides, their volatility and their contribution to collective dose, principally in the thyroid gland. 6 The default value of receptor height was taken equal to 1.5 m.…”

Section: Source Term and Accidental Release Scenariomentioning

confidence: 99%

“…1), developed at Lawrence Livermore National Laboratory, University of California, USA. 6,7 The total damage of fuel element cladding with a maximum release of radioactivity from the reactor core and building was considered. 5 The Hotspot code includes radiation dosimetry methodologies recommended by the International Commission on Radiological Protection (ICRP) and summarized in Federal Guidance Reports No.…”

Section: Introductionmentioning

confidence: 99%

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Comparative Radiation Dose Study of a Hypothetical Accident in a Research Reactor

Dahia¹,

Merrcoche²,

Dadda³

et al. 2022

Kemija U Industriji

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This study is a contribution for radiation dose calculations of a hypothetical accident of a 1 MW research reactor Triga Mark II using HotSpot code. A postulated accidental release of noble gases and halogens were considered. The total effective dose (TED) was estimated for 1 day and 50 years after release. The total damage of fuel element cladding with a maximum radioactivity was considered. The obtained results show minimal TED values at the beginning of the release and at a shorter distance from the source. The maximum calculation results are acceptable and below the recommended public dose limit.

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Radiological Dose Assessment for the Ghana Research Reactor-1 at Shutdown Using Dispersion Model: Conversion from High-Enriched Uranium to Low-Enriched Uranium Fuel

Cited by 3 publications

References 4 publications

Assessment of radiological consequence of a hypothetical accident at the Ghana Research Reactor-1 facility based on terrorist attack

Assessment of radiological consequence of a hypothetical accident at the Ghana Research Reactor-1 facility based on terrorist attack

Numerical Dose Assessment and Short-term Radioactivity Impact on Foodstuff for Continuous Release from of TRIGA Mark II Research Reactor

Comparative Radiation Dose Study of a Hypothetical Accident in a Research Reactor

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