Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Developing a Nuclear Neutronic Code in Rectangular, Triangular and Cylindrical Geometry

Document Type : Research Paper

Authors

A Pazirandeh
M.H Jalili Behabadi
P Abadi
M Mohammadnia
Abstract
A three-dimensional reactor static code for calculation of flux, power, multiplication factor and also power peaking factor in rectangular, triangular and cylindrical geometry core has been developed and benchmarked. For solution of the time independent neuron diffusion equation a finite difference method was used. To solve the equation with finite difference method, the speed of the applied numerical calculation is a major subject of interest, especially when the number of nodes increases. For this reason using an appropriate method to make the calculation faster is considered as the main priority. The aim of this paper is to present this three-dimensional nuclear reactor code with an emphasis made on the comparison between the advanced iterative algorithms in this code.
 

Highlights

  1. J. J. Duderstadt, Louis J. Hamilton, Nuclear Reactor Analysis, Jone Wiley & Sons (1976).

     

  2. K. Almenas, Introduction to Nuclear Reactor Physics, Springer publishing Co (1992).

 

  1. Y. A. Shatilla, A sample quadratic nodal model for hexagonal geometry, Massachusetts institute of technology, September (1992).

 

  1. T. Downar, D. Lee, Y. Xu, T. Kozlowski, PARCS v2.6 U.S. NRC Core Neutronics Simulator THEORY MANUAL, School of Nuclear Engineering Purdue University (2004).

 

  1. RSICC computer code collection, CITATION-  LDI2, OAK RIDGE national laboratory (1971).

 

  1. Computational Benchmark Problems Committee of the Mathematics and Computation Division of The American Nuclear Society, ANL-7416 Supplement 2, Argonne Code Center (1977).

 

  1. http://aerbench.kfki.hu/aerbench/FCM101.doc.

     

Keywords

Diffusion Equation
Multi-Dimension Geometry
Finite Difference Method
Optimization Factor Finite Difference
Gauss-Seidel

  1. J. J. Duderstadt, Louis J. Hamilton, Nuclear Reactor Analysis, Jone Wiley & Sons (1976).

     

  2. K. Almenas, Introduction to Nuclear Reactor Physics, Springer publishing Co (1992).

 

  1. Y. A. Shatilla, A sample quadratic nodal model for hexagonal geometry, Massachusetts institute of technology, September (1992).

 

  1. T. Downar, D. Lee, Y. Xu, T. Kozlowski, PARCS v2.6 U.S. NRC Core Neutronics Simulator THEORY MANUAL, School of Nuclear Engineering Purdue University (2004).

 

  1. RSICC computer code collection, CITATION-  LDI2, OAK RIDGE national laboratory (1971).

 

  1. Computational Benchmark Problems Committee of the Mathematics and Computation Division of The American Nuclear Society, ANL-7416 Supplement 2, Argonne Code Center (1977).

 

  1. http://aerbench.kfki.hu/aerbench/FCM101.doc.

     

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