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Neutron Noise Calculation using Nodal Expansion Method

Vosoughi, Javad | 2016

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  1. Type of Document: M.Sc. Thesis
  2. Language: Farsi
  3. Document No: 49515 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Vosoughi, Naser; Hosseini, Abolfazl
  7. Abstract:
  8. The present M.Sc. thesis consists of two sections including the static calculation and neutron noise calculation in rectangular and hexagonal geometries. The multi-group, two dimensional neutron diffusion equations and corresponding adjoint equations are solved in the static calculation. The spatial discretization of equations is based on Average Current Nodal Expansion Method (ACNEM). Size of nodes is the same size of the fuel assemblies in modeling both of rectangular and hexagonal geometries. The results are benchmarked against the valid results for BIBLIS-2D and IAEA-2D benchmark problems. In the second section, neutron noise calculations are performed for two types of noise sources, i.e. absorber of variable strength and Inadvertent Loading and Operation of a Fuel Assembly in an Improper Position (ILOFAIP). The adjoint of noise equation are solved using similar method used in forward calculation. Comparison of the calculated neutron noise at zero frequency with the result of static calculation, utilizing the result of adjoint noise calculations and qualitative comparison with similar report result are three different procedures to validate the neutron noise calculations. In the neutron noise calculations, the fluctuations are only considered in macroscopic absorption, fission and scattering cross sections and the fluctuations in neutron diffusion are ignored
  9. Keywords:
  10. Neutron Flux ; Neutron Noise ; Multiplication Factor ; Expansion ; Average Current Control ; Fuel Asembely

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