A polynomial nodal method is developed to solve few-group neutron diffusion equations in cartesian geometry. In this article, the effective multiplication factor, group flux and power distribution based on the nodal polynomial expansion procedure is presented. In addition, by comparison of the results the superiority of nodal expansion method on finite-difference and finite-element are fully demonstrated. The comparison of the results obtained by these method with those of the well known benchmark problems have shown that they are in very good agreement.
Highlights
1.R. Stamm'ler, M. Abbate, “Methods of steady-state reactor physics in nuclear design,” Academic Press (1983).
2.H. Finnemann, F. Bennewitz, MR. Wagner, “Interface current techniques for multidimensional reactor calculations,” Atomkernenergie, 30, 123-128 (1977).
3.B. Xia, Z. Xie, “Flux expansion method for solving multigroup neutron difusion equations in hexagonal-z geometry,” Annals of Nuc Energy, 33, 370-376 (2006).
4.J.J. Duderstandt, L.J. Hamilton, “Nuclear reactor analysis,” John Wiley & Sons, New York (1976).
5.C.M. Kang, K.F. Hansen, “Finite element methods for reactor analysis,” Nuc Sci Eng, Vol. 51, 456-495 (1973).
6.E.L. Wachspress, “Iterative solution of elliptic systems and application to the neutron diffusion equations of reactor physics,” Prentice Hall, Englwood cliffs (1966).
7.Argonne Code Center, “Benchmark problem book,” ANL-7416, Supplement 2 (1977).
8.A.F. Henry, “Refinements in accuracy of coarse-mesh finite difference solutions of the group diffusion equations,” Seminar on Nuclear Reactor Calculations, IAEA/SM, 154/21, 447 (1972).
1.R. Stamm'ler, M. Abbate, “Methods of steady-state reactor physics in nuclear design,” Academic Press (1983).
2.H. Finnemann, F. Bennewitz, MR. Wagner, “Interface current techniques for multidimensional reactor calculations,” Atomkernenergie, 30, 123-128 (1977).
3.B. Xia, Z. Xie, “Flux expansion method for solving multigroup neutron difusion equations in hexagonal-z geometry,” Annals of Nuc Energy, 33, 370-376 (2006).
4.J.J. Duderstandt, L.J. Hamilton, “Nuclear reactor analysis,” John Wiley & Sons, New York (1976).
5.C.M. Kang, K.F. Hansen, “Finite element methods for reactor analysis,” Nuc Sci Eng, Vol. 51, 456-495 (1973).
6.E.L. Wachspress, “Iterative solution of elliptic systems and application to the neutron diffusion equations of reactor physics,” Prentice Hall, Englwood cliffs (1966).
7.Argonne Code Center, “Benchmark problem book,” ANL-7416, Supplement 2 (1977).
8.A.F. Henry, “Refinements in accuracy of coarse-mesh finite difference solutions of the group diffusion equations,” Seminar on Nuclear Reactor Calculations, IAEA/SM, 154/21, 447 (1972).
Abdollahzadeh,M. and Boroushaki,M. (2009). Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies. Journal of Nuclear Science, Engineering and Technology (JONSAT), 30(2), 46-52.
MLA
Abdollahzadeh,M. , and Boroushaki,M. . "Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies", Journal of Nuclear Science, Engineering and Technology (JONSAT), 30, 2, 2009, 46-52.
HARVARD
Abdollahzadeh,M.,Boroushaki,M. (2009). 'Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies', Journal of Nuclear Science, Engineering and Technology (JONSAT), 30(2), pp. 46-52.
CHICAGO
M. Abdollahzadeh and M. Boroushaki, "Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies," Journal of Nuclear Science, Engineering and Technology (JONSAT), 30 2 (2009): 46-52,
VANCOUVER
Abdollahzadeh,M.,Boroushaki,M. Using Nodal Expansion Method in Calculation of Reactor Core with Square Fuel Assemblies. Journal of Nuclear Science, Engineering and Technology (JONSAT), 2009; 30(2): 46-52.
