Assessment of Radiological Impacts from Postulated Accident Conditions of HTGR: A Case Study in Serpong Nuclear Area
DOI:
https://doi.org/10.17146/tdm.2022.24.2.6613Keywords:
HTGR, Depressurization, Water Ingress, Radiological impacts, Radiation dosesAbstract
High-temperature gas-cooled reactor (HTGR) design has improved safety which relies on its TRISO-coated fuel particles that are considered as no failure even in accident conditions. However, the radiological impacts of accident conditions in HTGR are still important to be assessed. This research is aimed to perform a radiological impacts assessment of two postulated accidents of HTGR, which are depressurization and water ingress accidents. As a case study, a 10-MWt pebble-bed HTGR design named Reaktor Daya Eksperimental with the planned site located in Serpong Nuclear Area was chosen. The source terms from the accident conditions were estimated using the mechanistic source term model and the dose consequences were calculated using PC-COSYMA. The input data for PC-COSYMA, consisting of meteorological, population distribution, agricultural, and local farm data, were compiled based on the site data of the Serpong Nuclear Area. The radiological impacts were assessed based on individual and collective doses. The results showed that the highest dose will be received by the community within a radius of 250 m to the south from the reactor, amounting to about 7.22E-02 mSv and 3.04E-03 mSv from depressurization and water ingress accidents, respectively. It was also found that these accidents only result in minor radiological impacts since the highest dose obtained is still below the limit set by the national nuclear regulatory agency (BAPETEN) and do not require any countermeasures (iodine thyroid blocking, sheltering, evacuation, food ban, decontamination, and relocation).
References
Hartanto D., Liem P.H. Physics Study of Block/Prismatic-type HTGR Design Option for the Indonesian Experimental Power Reactor (RDE). Nucl. Eng. Des. 2020. 368(September):110821.
https://doi.org/10.1016/j.nucengdes.2020.110821
Liem P.H., Sembiring T.M., Tran H.N. Evaluation on Fuel Cycle and Loading Scheme of the Indonesian experimental power reactor (RDE) design. Nucl. Eng. Des. 2018. 340(October):245-59.
https://doi.org/10.1016/j.nucengdes.2018.10.004
Wang J., Zhang L., Qu J., Tong J., Wu G. Rapid Accident Source Term Estimation (RASTE) for Nuclear Emergency Response in High Temperature Gas Cooled Reactor. Ann. Nucl. Energy. 2020. 147:107654.
https://doi.org/10.1016/j.anucene.2020.107654
Ahangari R., Noori-Kalkhoran O., Sadeghi N. Radiological Dose Assessment for the Hypothetical Severe Accident of the Tehran Research Reactor and Corresponding Emergency Response. Ann. Nucl. Energy. 2017. 99:272-8.
https://doi.org/10.1016/j.anucene.2016.09.005
Ding H., Tong J., Raskob W., Zhang L. An Approach for Radiological Consequence Assessment under Unified Temporal and Spatial Coordinates Considering Multi-reactor Accidents. Ann. Nucl. Energy. 2019. 127:450-8.
https://doi.org/10.1016/j.anucene.2018.12.024
Kaviani F., Memarian M.H., Eslami-Kalantari M. Radioactive Impact on Iran and the World from a Postulated Accident at Bushehr Nuclear Power Plant. Prog. Nucl. Energy. 2021. 142(September):103991.
https://doi.org/10.1016/j.pnucene.2021.103991
Udiyani P.M., Setiawan M.B., Subekti M., Kuntjoro S., Pane J.S., Hastuti E.P., et al. Assessment of Dose Consequences Based on Postulated BDBA (Beyond Design Basic Accident) A-30MWt RSG-GAS after 30-year Operation. Prog. Nucl. Energy. 2021. 140:103927.
https://doi.org/10.1016/j.pnucene.2021.103927
Tang Z., Jiang S., Cai J., Li Q., Li X., Gong Z. Evaluating the Impact of Airborne Radionuclides Caused by the Fukushima Nuclear Accident on China Based on Global Atmospheric Dispersion. Prog. Nucl. Energy. 2021. 139(November 2020):103869.
https://doi.org/10.1016/j.pnucene.2021.103869
Ahn K. Il, Shin J.U., Kim W.T. An Assessment of Radiological Source Terms for Loss of Cooling and Coolant Accidents of a PWR Spent Fuel Pool. Prog. Nucl. Energy. 2020. 129(September):103513.
https://doi.org/10.1016/j.pnucene.2020.103513
Raja Shekhar S.S., Venkata Srinivas C., Rakesh P.T., Venkatesan R., Venkatraman B. Radiological Consequence Assessments using Time-varying Source Terms in ONERS- Decision Support System for Nuclear Emergency Response. Prog. Nucl. Energy. 2020. 127(May):103436.
https://doi.org/10.1016/j.pnucene.2020.103436
Tang Z., Cai J., Li Q., Zhao J., Li X., Yang Y. The Regional Scale Atmospheric Dispersion Analysis and Environmental Radiation Impacts Assessment for the Hypothetical Accident in Haiyang Nuclear Power Plant. Prog. Nucl. Energy. 2020. 125(May):103362.
https://doi.org/10.1016/j.pnucene.2020.103362
Hummel D.W., Chouhan S., Lebel L., Morreale A.C. Radiation Dose Consequences of Postulated Limiting Accidents in Small Modular Reactors to Inform Emergency Planning Zone Size Requirements. Ann. Nucl. Energy. 2020. 137:107062.
https://doi.org/10.1016/j.anucene.2019.107062
Ding H., Tong J., Wang Y., Zhang L. Development of Emergency Planning Zone for High Temperature Gas-cooled Reactor. Ann. Nucl. Energy. 2018. 111:347-53.
https://doi.org/10.1016/j.anucene.2017.08.039
Hanson D, Validation Status of Design Methods for Predicting Source Terms, Nucl Eng and Des. 2018. 329: 60-72,
https://doi.org/10.1016/j.nucengdes.2017.11.018
Husnayani I., Udiyani P.M. Radionuclide Characteristics of RDE Spent Fuels. J. Teknol. Reakt. Nukl. Tri Dasa Mega. 2018. 20(2):69.
https://doi.org/10.17146/tdm.2018.20.2.4101
Udiyani P.M., Husnayani I., Setiawan M.B., Kuntjoro S., Adrial H., Hamzah A. Estimation of the Radioactive Source Term From RDE Accident Postulation. J. Teknol. Reakt. Nukl. Tri Dasa Mega. 2019. 21(3):113.
https://doi.org/10.17146/tdm.2019.21.3.5583
Rudas C., Pázmándi T., Zagyvai P. Evaluation of an Improved Method and Software Tool for Confirming Compliance with Release Criteria for Nuclear Facilities. Ann. Nucl. Energy. 2021. 159:108332.
