An approach of radiological impact analysis due to a simulated accident of the TRIGA research reactor of Bangladesh

• Published in: Radiation physics and chemistry (Oxford, England : 1993) Vol. 219; p. 111689
• Main Authors: Khaer, M.A., Hoq, M.A., Hassan, S.M.T., Chowdhury, M.T., Rahman, M.M.
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.06.2024
• Subjects: HotSpot 3.1.2 code; Nuclear accident; Thyroid dose; Total effective dose equivalent (TEDE); TRIGA mark-II research reactor; Thyroid dose; TRIGA mark-II research reactor; HotSpot 3.1.2 code; Nuclear accident; Total effective dose equivalent (TEDE)
• ISSN: 0969-806X; 1879-0895
• DOI: 10.1016/j.radphyschem.2024.111689

The present study focused on the radiological impact analysis by assessing radiological doses due to a postulated TRIGA Mark-II research reactor accident at AERE, Savar, Dhaka, Bangladesh. Core inventory and source term of radionuclides from different groups such as noble gas, halogen, tellurium, alkali metal, lanthanide, alkaline earth metal, cerium and transition metal were analyzed for 365 days of operation at full power (3 MWth) due to a postulated nuclear accident. The HotSpot code was used for the dose calculation, and the dose values of TED, and Thyroid were calculated for a 40 km radius from the reactor site. Local meteorological data from Bangladesh Meteorological Department were used for the dose assessment and doses were calculated in the three dominant directions such as South, Southeast, and West. The TED and Thyroid dose values are assessed and compared to the PAZs dose criteria of the U.S. Environmental Protection Agency. It is found that doses are higher in stability class F, and evacuation, sheltering, and iodine prophylaxis are needed at longer distances. Since outside of the AERE campus is densely populated, these calculated data may help to ensure radiological safety by taking required protective actions like evacuation, sheltering, and iodine tablet consumption for the same type of accidental situation. •Source term analysis of five major radionuclides for 365 days of operation at full power of the reactor.•Dose calculation using the HotSpot 3.1.2 codes for day and night time in the three dominant directions.•Observation of maximum TEDE and Thyroid CDE dose values.•Assessment of Evacuation and Sheltering distances for both day and night time.