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Development of a Multi-Dimensional and Multi-Group Code for Black and Gray Dancoff Factor Calculation Based on Monte Carlo Method in Various Geometries

Ghaderi Mazaher, Meysam | 2011

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 42628 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Vossoughi, Nasser
  7. Abstract:
  8. Most of the nuclear codes used equivalence between a homogeneous and heterogeneous region to calculate resonance shelf-shielding. when fuels are together in a lattice arrangement, As a good approximation in the resonance shelf-shielding calculation, one could only consider a single fuel lump and consider the effect of neighbor fuels with a correction factor, i.e. the Dancoff coefficient. So far, several methods have used for calculating the Dancoff coefficient, but accuracy of these methods did not improved. In this thesis a computer program (MCDAN-3D) is developed for calculation of the multi-dimension and multi-group black and gray Dancoff coefficient, based on Monte Carlo, escape probability, neutron free flight and finite flight methods. This program is originally based on neutron collision probability. It calculates the probability that a neutron which is produced isotropically from fuel surface, has its first collision in the neighbor fuel. The developed program is enable to calculate the Dancoff coefficient each arbitrary arrangement of fuel with different dimensions and control rods that in various lengths entered the reactor core. Furthermore this program is enable to simulate fuels with homogeneous and heterogeneous composition in Pebble bed and HTR reactors. Also it can produce the place of Triso particles in fuel pebble and fuel rod randomly. The fuel may have different cross sections, so the program can calculate black and gray Dancoff coefficients. Finally, clad and moderator effects are considered and the sensitivity of Dancoff coefficient with fuel arrangements, number of Triso particles and neutron energy have been studied. The calculated dancoff coefficients are then used to the cell criticality calculations by the WIMS code
  9. Keywords:
  10. Free Flight ; Monte Carlo Method ; Cell Critically Calculation ; Gray Dancoff ; Black Dancoff

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