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Research on the Local Neutronics Thermal-Hydraulic Coupled Response of a PWR During Hypothetical Blockage Scenarios

[+] Author Affiliations
Xiaorong Li, Shinian Peng

Nuclear Power Institute of China, Chengdu, Sichuan, China

Paper No. ICONE22-30911, pp. V003T06A039; 5 pages
doi:10.1115/ICONE22-30911
From:
  • 2014 22nd International Conference on Nuclear Engineering
  • Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security
  • Prague, Czech Republic, July 7–11, 2014
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-4593-6
  • Copyright © 2014 by ASME

abstract

The phenomenon of the partial flow blockage of a fuel assembly in a reactor core is investigated with a coupled 3D neutronics/thermal-hydraulics code in order to account for the space reactivity feedback effect which is of great importance during hypothetical blockage scenarios. This paper identifies the neutronics thermal-hydraulics coupled response in the blocked assembly during the transient and analyzes the details of the phenomenon.

Copyright © 2014 by ASME

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