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Development of a 3D program for calculation of multigroup Dancoff factor based on Monte Carlo method in cylindrical geometry

Ghaderi Mazaher, M ; Sharif University of Technology | 2015

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  1. Type of Document: Article
  2. DOI: 10.1016/j.anucene.2014.11.045
  3. Publisher: Elsevier Ltd , 2015
  4. Abstract:
  5. Evaluation of multigroup constants in reactor calculations depends on several parameters, the Dancoff factor amid them is used for calculation of the resonance integral as well as flux depression in the resonance region in the heterogeneous systems. This paper focuses on the computer program (MCDAN-3D) developed for calculation of the multigroup black and gray Dancoff factor in three dimensional geometry based on Monte Carlo and escape probability methods. The developed program is capable to calculate the Dancoff factor for an arbitrary arrangement of fuel rods with different cylindrical fuel dimensions and control rods with various lengths inserted in the reactor core. The initiative calculates the black and gray Dancoff factor versus generated neutron flux in cosine and constant shapes in axial fuel direction. The effects of clad and moderator are followed by studying of Dancoff factor's sensitivity with variation of fuel arrangements and neutron's energy group for CANDU37 and VVER1000 fuel assemblies. MCDAN-3D outcomes poses excellent agreement with the MCNPX code. The calculated Dancoff factors are then used for cell criticality calculations by the WIMS code
  6. Keywords:
  7. Cell criticality ; Monte Carlo method ; Control rods ; Criticality (nuclear fission) ; Cylinders (shapes) ; Fuels ; Sensitivity analysis ; Black ; Criticality calculations ; Dancoff ; Gray ; Heterogeneous systems ; MCNP ; Multi-group constants ; Three dimensional geometry ; Monte Carlo methods
  8. Source: Annals of Nuclear Energy ; Volume 78 , 2015 , Pages 49-59 ; 03064549 (ISSN)
  9. URL: http://www.sciencedirect.com/science/article/pii/S0306454914006549