Simulation of the Radioactive Release of 90Sr from a Hypothetical Severe Accident in a Nuclear Power Plant for Use as a Possible Decision Support System (Dss)
DOI:
https://doi.org/10.48165/jntas.2026.14.01.04Keywords:
NPP, DSS, TEDE, Accident, HotSpot, CodeAbstract
These days, one of the most important safety and security concerns of the new century is the use of Decision Support Systems, such as software to assist special- ists during emergency preparedness operations in the event of an atypical incident (such as a radioactive diffusion). Natural or man - made accident that have a detrimental effect on the environment and public health. The DSS is required to enhance the prevention phase, which is important in an emergency preparedness system, as well as to ensure that the right safety route is chosen to promote the safety of operators and the populace in the event of a disaster. The HOT SPOT code, a free license code, was utilized in this work to model radioactive accident scenarios. The 90 Sr contamination was chosen to simulate a worst-case scenario. It is an accident because the release of 90 Sr (28.8 years) into the environment fol- lowing a nuclear accident can have detrimental long-term effects on the ecosystem and human health. It can contaminate soil, water, and living things in the environ- ment for decades. Its radioactive beta emissions, which can cause leukemia, bone cancer, and other illnesses, are the main health hazards. Because of its similarity to calcium, it is readily absorbed by bones, putting both humans and animals at danger for long-term radiation exposure. Public safety, environmental monitor- ing, and pollution remediation are the main areas of focus for efforts to reduce these risks. The radioactive diffusion caused by an accident has been simulated using the HOT SPOT algorithm. In order to determine the actual viability of using HOT SPOT as DSS during the prevention and/or intervention emergency phases, this paper analyzes and discusses the scenario used in the simulation to evaluate its spread from data for the Total Effective Dose (TEDE) and the deposition of material on the ground , the results showed that maximum Total Effective Dose Equivalent (TEDE) occurred within the first kilometer from the source (0.19–0.28 Sv), with ground deposition peaking at 0.2–0.6 km (2.6×10⁴–3.8×10⁴ kBq/m²).
References
An, H. Y., Kang, Y. H., Song, S. K., & Kim, Y. K. (2016). Atmospheric dispersion characteristics of radioactive materials according to the local weather and emission conditions. Journal of Radiation Protection and Research, 41(4), 315–327.
Anvari, A., & Safarzadeh, L. (2012). Assessment of the total effective dose for accidental release from the Tehran Research Reactor. Annals of Nuclear Energy, 50, 251–255.
Bellecci, C., Gaudio, P., Gelfusa, M., Malizia, A., Richetta, M., Serafini, C., & Ventura, P. (2010). Planetary boundary layer (PBL) monitoring by means of two laser radar systems: Experimental results and comparison. Proceedings of SPIE, 7832, 78320X.
Carestia, M., Malizia, A., Oscar, B., Fiorini, E., Soave, P. M., Latini, G., Cenciarelli, O., D’Amico, F., Bellecci, C., & Gaudio, P. (2016). Use of the “HotSpot” code for safety and security analysis in nuclear power plants: A case study. Environmental Engineering and Management Journal, 15(4), 905–912.
Cenciarelli, O., Malizia, A., Marinelli, M., Pietropaoli, S., Gallo, R., D’Amico, F., Bellecci, C., Fiorito, R., Gucciardino, A., & Gaudio, P. (2013a). Evaluation of biohazard management of the Italian national fire brigade. Defence S&T Technical Bulletin, 6, 33–41.
Cenciarelli, O., Rea, S., Carestia, M., D’Amico, F., Malizia, A., Bellecci, C., Gaudio, P., Gucciardino, A., & Fiorito, R. (2013b). Bioweapons and bioterrorism: A review of history and biological agents. Defence S&T Technical Bulletin, 6, 111–129.
Dahia, A., Merrouche, D., & Rezoug, M. T. (2018). Radioactive contamination control by atmospheric dispersion assessment of airborne indicator contaminants: Numerical model validation. Environmental Monitoring and Assessment, 23, 401–414.
Environmental Protection Agency. (1988). Limiting values radionuclide intake and air concentration, and dose conversion factors for inhalation, submersion, and ingestion (Federal Guidance Report No. 11). U.S. Environmental Protection Agency.
Gallo, R., De Angelis, P., Malizia, A., Conetta, F., & Di Giovanni, D. (2013). Development of a georeferencing software for radiological diffusion in order to improve the safety and security of first responders. Defence S&T Technical Bulletin, 6, 21–32.
Gaudio, P., Malizia, A., & Lupelli, I. (2010). Experimental and numerical analysis of dust resuspension for supporting chemical and radiological risk assessment in a nuclear fusion device. Proceedings of the International Conference on Mathematical Models for Engineering Science, 134–147.
Hawley, S. C., & Kathren, R. L. (1982). Credible accident analyses for TRIGA and TRIGA-fueled reactors. Pacific Northwest Laboratory.
Homann, S. G. (2011). HotSpot health physics codes version 2.07.2 user’s guide. National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory.
Homann, S. G., & Aluzzi, F. (2013). HotSpot health physics codes version 3.0 user’s guide. National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory.
Homann, S. G., & Aluzzi, F. (2020). HotSpot health physics codes version 3.1.2 user’s guide (LLNL-SM-636474). National Atmospheric Release Advisory Center, Lawrence Livermore National Laboratory.
International Atomic Energy Agency. (2014). Radiation protection and safety of radiation sources: International basic safety standards (General Safety Requirements Part 3). International Atomic Energy Agency.
International Atomic Energy Agency. (2001). Generic models for use in assessing the impact of discharges of radioactive substances to the environment (Safety Reports Series No. 19). International Atomic Energy Agency.
International Atomic Energy Agency. (2010). Programmes and systems for source and environmental radiation monitoring (Safety Reports Series No. 64). International Atomic Energy Agency.
International Commission on Radiological Protection. (1979). Limits for intakes of radionuclides by workers. Annals of the ICRP, 2(3–4). https://www.icrp.org/publication.asp?id=ICRP%20Publication%2030%20(Part%201)
International Commission on Radiological Protection. (1990). Recommendations of the International Commission on Radiological Protection (ICRP Publication 60). Annals of the ICRP, 21(1–3).
International Commission on Radiological Protection. (1991). Recommendations of the International Commission on Radiological Protection. Annals of the ICRP, 21(1–3).
International Commission on Radiological Protection. (1992). Principles for intervention for protection of the public in a radiological emergency. Annals of the ICRP, 22(4).
International Commission on Radiological Protection. (1995). Age-dependent doses to the members of the public from intake of radionuclides: Part 5. Compilation of ingestion and inhalation coefficients (ICRP Publication 72). Annals of the ICRP, 26(1).
International Commission on Radiological Protection. (2005). Basis for dosimetric quantities used in radiological protection. International Commission on Radiological Protection.
U.S. Nuclear Regulatory Commission. (2000). Alternative radiological source terms for evaluating design basis accidents at nuclear power reactors (Regulatory Guide 1.183). U.S. Nuclear Regulatory Commission.
Mahmoud, R. M., Massoud, E., Ahmed, M. M., Ezz El-Din, M. R., Aziz, M., & Rizk, R. A. (2012). Study on dispersion of airborne radionuclides released from nuclear power plant under hypothetical accidental scenario. Journal of Nuclear and Radiation Physics, 7(1–2), 55–70.
Malek, M. A., Chisty, K. J. A., & Rahman, M. M. (2012). Dose distribution of 131I, 132I, 133I, 134I, and 135I due to a hypothetical accident of TRIGA Mark-II research reactor. International Journal of Basic and Applied Sciences, 1, 244–259.
Musauddin, A., & Kim, J. (2019). Offsite radiological consequence analysis of hypothetical accidents for APR1400. Journal of Radiation Industry, 13(2), 147–155.
Muswema, J. L., Ekoko, G. B., Lobo, J. K. K., & Lukanda, V. M. (2016). TRICO II core inventory calculation and its radiological consequence analyses. Journal of Nuclear Radiation Sciences, 2(2), 024501.
Pazienza, M., Britti, M. S., Carestia, M., Cenciarelli, O., D’Amico, F., Malizia, A., Bellecci, C., Gaudio, P., Gucciardino, A., Bellino, M., Lancia, C., Tamburrini, A., & Fiorito, R. (2013). Application of realtime PCR to identify residual bio-decontamination of confined environments after hydrogen peroxide vapor treatment: Preliminary results. Journal of Microbial & Biochemical Technology, 6, 24–28.
Pazienza, M., Britti, M. S., Carestia, M., Cenciarelli, O., D’Amico, F., Malizia, A., Bellecci, C., Fiorito, R., Gucciardino,A., Bellino, M., Lancia, C., Tamburrini, A., & Gaudio, P. (2014). Use of particle counter system for the optimization of sampling, identification and decontamination procedures for biological aerosols dispersion in confined environment. Journal of Microbial & Biochemical Technology, 6, 43–48.
Rentai, Y. (2011). Atmospheric dispersion of radioactive material in radiological risk assessment and emergency response. Progress in Nuclear Science and Technology, 1, 7–13.
United Nations Scientific Committee on the Effects of Atomic Radiation. (2000). Sources and effects of ionizing radiation: UNSCEAR 2000 report to the General Assembly (Vol. II, Annex J). United Nations.
U.S. Nuclear Regulatory Commission. (2013a). Total effective dose equivalent (TEDE). https://www.nrc.gov/reading-rm/basic-ref/glossary/total-effective-dose-equivalent-tede
U.S. Nuclear Regulatory Commission. (2013b). Deep-dose equivalent (DDE). https://www.nrc.gov/reading-rm/basic-ref/glossary/deep-dose-equivalent-dde
Voigt, G., & Fesenko, S. (2009). Radioactivity in the environment: Remediation of contaminated environments (Vol. 14). Elsevier.
Published
Issue
Section
License
Copyright (c) 2026 Ahmed O S, Salman Kh A (Author)
This work is licensed under a Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International License.
