In a reactor, for every 100 neutrons emitted in fission, 10 neutrons escape while slowing down,...

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In a reactor, for every 100 neutrons emitted in fission, 10 neutrons escape while slowing down, 15 escape after having slowed down to thermal energies, and 5 absorbed while slowing down. Of those neutrons absorbed at thermal energies, 60 percent are absorbed in fissile material. Please assume that the n value of the reactor is 2.07. What is the multiplication factor of the reactor ? In a reactor, for every 100 neutrons emitted in fission, 10 neutrons escape while slowing down, 15 escape after having slowed down to thermal energies, and 5 absorbed while slowing down. Of those neutrons absorbed at thermal energies, 60 percent are absorbed in fissile material. Please assume that the n value of the reactor is 2.07. What is the multiplication factor of the reactor ?