Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh

Radiological dose distribution owing to the deposition of 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe on ground and immersion considering a postulated accident of TRIGA Mark-II research reactor has been assessed. The radiological dose distribution has been carried out in various directions with...

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Main Authors: K. M. Z. Zihan, M. A. Hoq, M. A. Khaer, M. T. Chowdhury, M. M. Rahman, M. S. Islam
Format: Article
Language:English
Published: Center for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN) 2022-12-01
Series:Atom Indonesia
Subjects:
Online Access:https://aij.batan.go.id/index.php/aij/article/view/1227
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author K. M. Z. Zihan
M. A. Hoq
M. A. Khaer
M. T. Chowdhury
M. M. Rahman
M. S. Islam
M. M. Rahman
author_facet K. M. Z. Zihan
M. A. Hoq
M. A. Khaer
M. T. Chowdhury
M. M. Rahman
M. S. Islam
M. M. Rahman
author_sort K. M. Z. Zihan
collection DOAJ
description Radiological dose distribution owing to the deposition of 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe on ground and immersion considering a postulated accident of TRIGA Mark-II research reactor has been assessed. The radiological dose distribution has been carried out in various directions with the help of Gaussian Diffusion Model. Local meteorological data such as average wind speed, frequency, etc. has been collected and evaluated for various directions around the reactor site. For all the dominant directions, the maximum dose values due to 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, 138Xe and the total (131mXe + 133mXe + 133Xe + 135mXe + 135Xe + 138Xe) were observed within the limit 3.03E-7–1.23E-4 µSv/h, 1.01E-5–4.09E-3 µSv/h, 0.0003–0.14 µSv/h, 2.29E-5–9.26E-3 µSv/h, 0.002 –1.111 µSv/h, 1.11E-5–4.55E-3 µSv/h, and 0.003–1.269 µSv/h, respectively. Dose distribution was found to be dominant due to immersion and the contribution was 87.55 %. There is shortage of data regarding the release of radioxenon in the atmosphere during nuclear accident especially in the case of TRIGA type research reactor. This paper is the first such detailed study on atmospheric release of radioxenon and its dose distribution for a full power- reactor and the consequences towards the environment and public health. The result can be applied to develop the radiological protective measures and to prepare an emergency response plan for the TRIGA reactor site.
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spelling doaj.art-fcf32b90b39448f3a8d0505fc89dd7532022-12-23T13:34:59ZengCenter for Development of Nuclear Informatics, National Nuclear Energy Agency (BATAN)Atom Indonesia0126-15682022-12-0148321522310.17146/aij.2022.1227498Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in BangladeshK. M. Z. Zihan0M. A. Hoq1M. A. Khaer2M. T. Chowdhury3M. M. Rahman4M. S. Islam5M. M. Rahman6Department of Physics, Jahangirnagar University, Savar, Dhaka, BangladeshInstitute of Energy Science, Bangladesh Atomic Energy Commission, Dhaka, BangladeshInstitute of Energy Science, Bangladesh Atomic Energy Commission, Dhaka, BangladeshInstitute of Energy Science, Bangladesh Atomic Energy Commission, Dhaka, BangladeshDepartment of Physics, Jahangirnagar University, Savar, Dhaka, BangladeshDepartment of Physics, Jahangirnagar University, Savar, Dhaka, BangladeshDepartment of Physics, Jahangirnagar University, Savar, Dhaka, BangladeshRadiological dose distribution owing to the deposition of 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, and 138Xe on ground and immersion considering a postulated accident of TRIGA Mark-II research reactor has been assessed. The radiological dose distribution has been carried out in various directions with the help of Gaussian Diffusion Model. Local meteorological data such as average wind speed, frequency, etc. has been collected and evaluated for various directions around the reactor site. For all the dominant directions, the maximum dose values due to 131mXe, 133mXe, 133Xe, 135mXe, 135Xe, 138Xe and the total (131mXe + 133mXe + 133Xe + 135mXe + 135Xe + 138Xe) were observed within the limit 3.03E-7–1.23E-4 µSv/h, 1.01E-5–4.09E-3 µSv/h, 0.0003–0.14 µSv/h, 2.29E-5–9.26E-3 µSv/h, 0.002 –1.111 µSv/h, 1.11E-5–4.55E-3 µSv/h, and 0.003–1.269 µSv/h, respectively. Dose distribution was found to be dominant due to immersion and the contribution was 87.55 %. There is shortage of data regarding the release of radioxenon in the atmosphere during nuclear accident especially in the case of TRIGA type research reactor. This paper is the first such detailed study on atmospheric release of radioxenon and its dose distribution for a full power- reactor and the consequences towards the environment and public health. The result can be applied to develop the radiological protective measures and to prepare an emergency response plan for the TRIGA reactor site.https://aij.batan.go.id/index.php/aij/article/view/1227radiological doseimmersionground depositiongaussian diffusion factorsafety.
spellingShingle K. M. Z. Zihan
M. A. Hoq
M. A. Khaer
M. T. Chowdhury
M. M. Rahman
M. S. Islam
M. M. Rahman
Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
Atom Indonesia
radiological dose
immersion
ground deposition
gaussian diffusion factor
safety.
title Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
title_full Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
title_fullStr Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
title_full_unstemmed Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
title_short Dose Distribution of Radioxenon Due to a Hypothetical Accident of TRIGA Research Reactor in Bangladesh
title_sort dose distribution of radioxenon due to a hypothetical accident of triga research reactor in bangladesh
topic radiological dose
immersion
ground deposition
gaussian diffusion factor
safety.
url https://aij.batan.go.id/index.php/aij/article/view/1227
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