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Azadifar, M., Shayesteh, M., Karimi, J. (2024). Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code. Electronic and Cyber Defense, 14(4), 253-263.
Mohammad Azadifar; Mohsen Shayesteh; Javad Karimi. "Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code". Electronic and Cyber Defense, 14, 4, 2024, 253-263.
Azadifar, M., Shayesteh, M., Karimi, J. (2024). 'Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code', Electronic and Cyber Defense, 14(4), pp. 253-263.
Azadifar, M., Shayesteh, M., Karimi, J. Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code. Electronic and Cyber Defense, 2024; 14(4): 253-263.

Simulation of Radioactive Material Release Resulting from a Hypothetical Accident for ABV Reactor Using RASCAL Code

علوم و فناوریهای پدافند نوین
Article 4, Volume 14, Issue 4 - Serial Number 54, January 2024, Pages 253-263
Document Type: Original Article
Authors
Mohammad Azadifar1; Mohsen Shayesteh* 2; Javad Karimi3
1Master's student, Imam Hossein University (AS), Tehran, Iran
2Associate Professor, Imam Hossein University, Tehran, Iran
3Researcher, Imam Hossein University . Tehran, Iran
Receive Date: 05 October 2023,  Revise Date: 15 December 2023,  Accept Date: 25 December 2023 
Abstract
Dose evaluation of radioactive materials is one of the main safety categories of reactors and nuclear facilities. The spread of radioactive materials, which may be caused by an accident in a nuclear facility, can cause radiation hazards to humans and the environment, in such a situation, the dose should be evaluated and, if necessary, appropriate control measures should be taken into account. In this article, it is assumed that the ABV reactor, which is a small modular reactor, has been installed in order to supply energy to industrial facilities around Mobarake city, located in Isfahan province. The main goal of this research is to investigate the atmospheric release of cesium-134 and cesium-137 caused by a hypothetical core meltdown incident in this reactor. The amount of cesium-134 and 137 radioisotopes present in the reactor core at the time of the accident, which was calculated in the previous works of the authors, is assumed as a radiation source. Then, using RASCAL software and assuming that the release time of these two radioisotopes is one hour, their atmospheric distribution has been investigated in two days after the accident and up to a radius of 80 km. In this research, total effective dose of TEDE, thyroid dose, inhaled CEDE, as well as the surface pollution of these two isotopes have been calculated and their distribution pattern up to 80 km distance from the accident site has been drawn.
Keywords
Small Modular Reactor; Nuclear Accident; RASCAL Code; Dose Rate; Cs-134; Cs-137
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