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Searched defs:nu_fission (Results 1 – 8 of 8) sorted by relevance

/dports/science/py-OpenMC/openmc-0.12.2/include/openmc/
H A Dxsdata.h81 xt::xtensor<double, 2> nu_fission; variable
H A Dparticle_data.h88 double nu_fission; //!< neutron production from fission member
141 double nu_fission; //!< macroscopic production xs member
/dports/science/openmc/openmc-0.12.2/include/openmc/
H A Dxsdata.h81 xt::xtensor<double, 2> nu_fission; variable
H A Dparticle_data.h88 double nu_fission; //!< neutron production from fission member
141 double nu_fission; //!< macroscopic production xs member
/dports/science/py-OpenMC/openmc-0.12.2/openmc/
H A Dmgxs_library.py325 def nu_fission(self): member in XSdata
851 def set_nu_fission(self, nu_fission, temperature=ROOM_TEMPERATURE_KELVIN): argument
1098 def set_nu_fission_mgxs(self, nu_fission, temperature=ROOM_TEMPERATURE_KELVIN, argument
/dports/science/openmc/openmc-0.12.2/openmc/
H A Dmgxs_library.py325 def nu_fission(self): member in XSdata
851 def set_nu_fission(self, nu_fission, temperature=ROOM_TEMPERATURE_KELVIN): argument
1098 def set_nu_fission_mgxs(self, nu_fission, temperature=ROOM_TEMPERATURE_KELVIN, argument
/dports/science/py-OpenMC/openmc-0.12.2/src/
H A Dmgxs.cpp555 double nu_fission = xs_t->nu_fission(cache[tid].a, gin); in sample_fission_energy() local
/dports/science/openmc/openmc-0.12.2/src/
H A Dmgxs.cpp555 double nu_fission = xs_t->nu_fission(cache[tid].a, gin); in sample_fission_energy() local