Neutronic analysis of HPLWR fuel assembly cluster

Tashakor, S ; Sharif University of Technology | 2012

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  1. Type of Document: Article
  2. DOI: 10.1016/j.anucene.2012.07.015
  3. Publisher: 2012
  4. Abstract:
  5. In the present study the neutronic analysis of fuel assembly cluster of the HPLWR is discussed. Neutronic calculations are performed using WIMS-D4 and CITATION codes. Thermal-hydraulic code containing the properties and specifications of the fuel assembly of HPLWR is utilized. The calculated axial power in each selected control volume is used in the thermal-hydraulic code to get the properties of the fluid and fuel needed for further neutronic analysis. The process of coupling continues until convergence is achieved. Finally, the obtained neutronic results including axial power distribution, neutron flux, and power peaking factors are discussed in the present article
  6. Keywords:
  7. Fuel assembly ; Axial power ; Axial power distribution ; Control volumes ; Fuel assembly ; HPLWR ; Neutronic analysis ; Neutronic calculations ; Neutronics ; Power peaking factor ; Supercritical pressures ; Thermal-hydraulic codes ; Reactor cores ; Fuels
  8. Source: Annals of Nuclear Energy ; Volume 50 , December , 2012 , Pages 38-43 ; 03064549 (ISSN)
  9. URL: http://www.sciencedirect.com/science/article/pii/S0306454912002629