Using RASCAL Code to Analyze the Postulated UF6 Fire Accident
In this research, the RASCAL code was used to simulate and analyze the postulated UF6 fire accident which may occur in the Institute of Nuclear Energy Research (INER). There are four main steps in this research. In the first step, the UF6 data of INER were collected. In the second step, the RASCAL analysis methodology and model was established by using these data. Third, this RASCAL model was used to perform the simulation and analysis of the postulated UF6 fire accident. Three cases were simulated and analyzed in this step. Finally, the analysis results of RASCAL were compared with the hazardous levels of the chemicals. According to the compared results of three cases, Case 3 has the maximum danger in human health.
Digital Object Identifier (DOI): doi.org/10.5281/zenodo.1474777Procedia APA BibTeX Chicago EndNote Harvard JSON MLA RIS XML ISO 690 PDF Downloads 628
 G. F. Athey, J. P. Rishel, J. V. Ramsdell, Jr., and J. J. Tomon, RASCAL 4.3: User’s Guide, U.S. Nuclear Regulatory Commission, Washington, DC, 2015.
 J. V. Ramsdell, Jr., G. F. Athey, and J. P. Rishel, RASCAL 4.3: Description of Models and Methods, U.S. Nuclear Regulatory Commission, Washington, DC, 2015.
 AIHA Guideline Foundation, 2016 ERPG/WEEL Handbook, 2016.
 R. Ahangari, O. Noori-Kalkhoran, N. Sadeghi, Radiological dose assessment for the hypothetical severe accident of the Tehran Research Reactor and corresponding emergency response, Annals of Nuclear Energy, Vol. 99, p. 272–278, 2017.
 Y. Zhao, L. Zhang, J. Tong, Development of rapid atmospheric source term estimation system for AP1000 nuclear power plant, Progress in Nuclear Energy, Vol. 81, p. 264-275, 2015.