Three-Dimensional Discrete Heterogeneous Finite Element Method and Code for Static Multi‐Group Neutron Diffusion
32nd Annual CNS Conference - 2011 June 05-08


Presented at:
32nd Annual CNS Conference
2011 June 05-08
Location:
Niagara Falls, Canada
Session Title:
Reactor and Radiation Physics II

Authors:
Elif-Can Aydogdu (UOIT)
Eleodor Nichita (UOIT)
  

Abstract

Accurate prediction of the neutron flux and power at the fuel pin level rather than at the fuel- assembly level requires, in principle, lengthy many-group transport-theory calculations using a detailed (fuel-pin level) geometrical representation of the core. Many-group fine-mesh diffusion theory, in conjunction with advanced fuel-pin-cell homogenization techniques, can also be used successfully to predict individual fuel pin powers but the computational effort is still sizeable because of the many regions and groups involved. A three dimensional diffusion code was developed which reduces the time taken by such full-core fine-mesh fine-group diffusion calculations by applying the finite-element method to the discrete form of the many-group fine- mesh diffusion equation and thus reducing the number of unknowns. Preliminary tests performed on a highly-heterogeneous three dimensional three-group model found the code to produce pin power results with a maximum error of 3.5% of the maximum pin power value, with an eight-fold reduction in computational time compared to a regular full-core fine-mesh calculation.

 

Individual Conference-Paper Copies (Electronic Where Available):

  • For CNS members, the first 5 copies per calendar year are free, and additional copies are $10 each.
  • For non-members, the price is $25 for the first Conference-paper copy in a request, and $10 each for additional copies of papers in the same conference and in the same request.
  • Contact the CNS office to order reprints.