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Abstract and Applied Analysis
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Abstract and Applied Analysis
/
2014
/
Article
/
Tab 1
/
Research Article
Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method
Table 1
2D homogeneous reactor cross sections.
(cm)
(cm)
(cm
−1
)
(cm
−1
)
(cm
−1
)
(cm
−1
)
(cm
−1
)
1.28205128205
0.666667
0.01
0.1
0.01
0.109017634020268
0.075