Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method

Table 16

Langenbuch reactor cross sections.

Material	𝐷1 (cm)	𝐷2 (cm)	Σ𝑎1 (cm^−1)	Σ𝑎2 (cm^−1)	Σ12 (cm^−1)	𝜐Σ𝑓1 (cm^−1)	𝜐Σ𝑓2 (cm^−1)
Comb.1	1.423913	0.356306	0.01040206	0.08766217	0.0175555	0.006477691	0.1127328
Comb.2	1.425611	0.350574	0.01099263	0.09925634	0.01717768	0.007503284	0.1378004
Absorbent	1.423913	0.356306	0.01095206	0.09146217	0.0175555	0.006477691	0.11273228
Reflector	1.634227	0.264002	0.002660573	0.04936351	0.02759693	0.0	0.0