Thermal Hydraulic and Neutronics Coupling Analysis for Plate Type Fuel in Nuclear Reactor Core

Table 4

The variations of neutron fission cross-sections with temperature in fuel.

Temperature (K)	ID extension
300	0.10c
325	0.11c
350	0.12c
375	0.13c
400	0.14c
425	0.15c
450	0.16c
475	0.17c
500	0.18c
525	0.19c
550	0.20c
575	0.21c
600	0.22c
625	0.23c
650	0.24c
675	0.25c