It is known that the average number of fast neutrons produced from each nuclear fission process of uranium-235 (235U) by means of a thermal neutron is equal to (v=2.42). For 235U:f=587b, and a=687b. For 238U:f=0a=2.75b Using the given information, calculate the value of the thermal fission coefficient (n) for the following cases: (a) Natural uranium nuclear fuel. (b) Nuclear fuel enriched to 12% uranium (2350). It is known that the average number of fast neutrons produced from each nuclear fission process of uranium-235 (235U) by means of a thermal neutron is equal to (v=2.42). For 235U:f=587b, and a=687b. For 238U:f=0a=2.75b Using the given information, calculate the value of the thermal fission coefficient (n) for the following cases: (a) Natural uranium nuclear fuel. (b) Nuclear fuel enriched to 12% uranium (2350)