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Preliminary Study of Microreactor Emergency Planning Zone

  • Erik Hisahara
  • , Christopher Balbier
  • , Saya Lee
  • , Rohan Biwalkar
  • , Sola Talabi

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

This study examines the dispersion patterns of a generic nuclear microreactor accident. The investigation involved a comprehensive analysis of χ/Q values across various receptor distances and directional orientations over time intervals ranging from immediate post-accident periods to 30 days. The computer code ARCON 2.0 was used to perform all simulations for the current study, with a meteorological data of approximately 1 year. Key findings indicate a consistent trend of elevated χ/Q values at a receptor distance of 15 meters, emphasizing the significance of proximity to the accident epicenter in assessing potential environmental impacts. Moreover, a discernible decrease in χ/Q values was observed within the near-field dispersion zone (15 to 50 meters), followed by stabilization in dispersion patterns beyond this range. Comparative analysis revealed notable differences in χ/Q values across different post-accident time intervals, suggesting a convergence towards equilibrium in dispersion trends over time. Future efforts intend to integrate these findings with accident source term data from TRIGA reactors to evaluate Emergency Planning Zone (EPZ) size determination.

Original languageEnglish (US)
Title of host publicationProceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024
PublisherAmerican Nuclear Society
Pages1381-1388
Number of pages8
ISBN (Electronic)9780894482212
DOIs
StatePublished - 2024
Event14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024 - Vancouver, Canada
Duration: Aug 25 2024Aug 28 2024

Publication series

NameProceedings of the 14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024

Conference

Conference14th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation, and Safety, NUTHOS 2024
Country/TerritoryCanada
CityVancouver
Period8/25/248/28/24

All Science Journal Classification (ASJC) codes

  • Computational Mechanics
  • Safety, Risk, Reliability and Quality
  • Nuclear and High Energy Physics
  • Fluid Flow and Transfer Processes

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