The total neutron flux in a uranium fueled reactor can be characterized by a fast flux component f1 composed entirely of 1 MeV neutrons and a thermal flux component f2 composed entirely of 0.025 eV neutrons; that is, all neutrons in the core are assumed to have energies of either 1 MeV or 0.025 eV. If 80% of the total neutron flux is fast, how many thermal (0.025 eV) neutrons exist in the reactor for every fast (1 MeV) neutron?