Computational Methods for Multidimensional Neutron Diffusion Problems

Table 1

Material data for the homogeneous core.

𝑔	Σ^𝑔𝑟	𝜈Σ^𝑔𝑓	𝐷^𝑔	Σ^𝑠𝑔→𝑔+1	Σ^𝑠𝑔→𝑔+2	𝜒^𝑔
	(cm^−1)	(cm^−1)	(cm)	(cm^−1)	(cm^−1)	—
1	0.3046𝐸−01	0.1076𝐸−01	2.11	0.2578𝐸−01	0.5164𝐸−03	0.7737
2	0.7060𝐸−02	0.3309𝐸−02	1.29	0.4705𝐸−02	—	0.2193
3	0.6316𝐸−02	0.4366𝐸−02	0.86	—	—	0.0070