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Study on Rod Ejection Accident With Coupled Neutronic/Thermal-Hydraulic Code

[+] Author Affiliations
Xiong Wang, Qiang Li, Dong Wang, Yong Ouyang, Xianghui Lu

China Nuclear Power Technology Research Institute, Shenzhen, China

Paper No. ICONE25-66656, pp. V008T09A022; 6 pages
  • 2017 25th International Conference on Nuclear Engineering
  • Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues
  • Shanghai, China, July 2–6, 2017
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5786-1
  • Copyright © 2017 by ASME


The Rod Ejection Accident (REA) belongs to the Reactivity-Initiated Accidents (RIA) category of accidents, and it is part of the licensing basis accident analyses required for pressurized water reactors (PWR). REA is usually an asymmetric transient where neutron kinetics and the thermal hydraulics are strongly coupled (through doppler feedback). With the aim of increasing simulation accuracy by eliminating conservatism at code interfaces, the coupled code SMART-FLICA which links 3D-neutron kinetics code SMART and thermal-hydraulic code FLICA III-F is used to perform REA transient. The analysis will characterize the PWR real plant phenomenology more accurately in the RIA category of accidents.

Copyright © 2017 by ASME
Topics: Accidents



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