Dose distribution of 131I, 132I, 133I, 134I, and 135I due to a hypothetical accident of TRIGA Mark-II research reactor.

Malek, Md. Abdul; Chisty, K. J. A.; Rahman, MM

doi:10.14419/ijbas.v1i3.110

Cited by 3 publications

(1 citation statement)

References 1 publication

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“…The same conclusions were found for the same type of reactor operated elsewhere by Hawley and Kathren. 2,5,[24][25][26] For the more stable atmospheric conditions, the maximum TED value decreases to a lower value due to less plume depletion (Fig. 4).…”

Section: Doses Calculationmentioning

confidence: 98%

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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Section: Doses Calculationmentioning

confidence: 98%

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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Assessment of Radiation Dose Associated with the Atmospheric Release of 41Ar from the TRIGA Mark-II Research Reactor in Bangladesh

Hoq,

Soner,

Khanom

et al. 2024

Science and Technology of Nuclear Installations

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A major concern for nuclear research reactors under normal operating conditions is that they may release radioactive elements into the atmosphere, endangering public health and the environment. The present study concentrated on the detailed radiological dose assessment resulting from the atmospheric release of 41Ar activity from the TRIGA Mark-II research reactor in Bangladesh during its normal operational condition at full power of 3 MW. The total effective dose equivalent (TEDE), ground deposition activity, organ-committed dose, and pathways dose values have been evaluated under different weather conditions using the HotSpot 3.1.2 code. The weather data have been gathered from the Bangladesh Meteorological Department (BMD), Dhaka. Two significant seasons with various weather stability effects have been considered for dose analysis. Atmospheric dispersion of 41Ar was evaluated using the Gaussian plume model. From the obtained results, the maximum TEDE of 4.06 × 10−9 Sv at 0.19 km distance from the reactor site for stability class B during the summer season is found to be well below the annual effective dose limit of 1 mSv recommended by the ICRP. During the rainy season, the maximum TEDE of 1.76 × 10−9 Sv at 0.92 km distance for stability class E is also found to be negligible compared to the dose limit. From the organ-committed dose analysis, skin is investigated as the highest dose absorber compared to other organs. The pathways dose analysis concludes that the submersion and ground shine doses are observed to be maximum at 0.20 km and 1.0 km distances for the summer and rainy seasons, respectively. Based on the identified results, dose values have been found to be within the limiting values, ensuring environmental and human health safety. Such comprehensive dose analysis due to the atmospheric release of 41Ar activity is very significant from the perspective of ensuring the radiological and environmental safety of research-type nuclear reactors under normal operational conditions.

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Source Term Atmospheric Release and Core Inventory Analysis for the PUSPATI TRIGA Reactor under Severe Accident Conditions

Sulaiman¹,

Mohamed²,

Rahim³

et al. 2019

JSM

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Dose distribution of 131I, 132I, 133I, 134I, and 135I due to a hypothetical accident of TRIGA Mark-II research reactor.

Abstract: An attempt has been made in the work to assess radiological dose due to the deposition of 131

Cited by 3 publications

References 1 publication

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

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

Assessment of Radiation Dose Associated with the Atmospheric Release of 41Ar from the TRIGA Mark-II Research Reactor in Bangladesh

Source Term Atmospheric Release and Core Inventory Analysis for the PUSPATI TRIGA Reactor under Severe Accident Conditions

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