Fission and reactions with multiple gammas

For fission reactions the multiplicity $\mu$ of the neutrons produced is given as a function of the energy E_yi of the incident neutron ( $\tt I\_number$ = 7 data). The probability density P(E_yi, E_yo) that an incident neutron with energy E_yi will produce a fission neutron with energy E_yo is also given. In this case output file from endep for average fission neutron energy contains the pairs

$$\mu \langle \rangle$$ (26)

where $\langle$E_yo$\rangle$ is the average energy of a single fission neutron as calculated from the integral (16). Note that the energy of the delayed fission neutrons is not included.

For some reactions, e. g., fission, the energy distribution of the gammas is given, along with their multiplicity as a function of the energy of the incident particle ( $\tt I\_number$ = 9 data). In these cases the output file from endep for average gamma energy includes the multiplicity as in (26).