Searched defs:nu_fission (Results 1 – 8 of 8) sorted by relevance
/dports/science/py-OpenMC/openmc-0.12.2/include/openmc/ |
H A D | xsdata.h | 81 xt::xtensor<double, 2> nu_fission; variable
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H A D | particle_data.h | 88 double nu_fission; //!< neutron production from fission member 141 double nu_fission; //!< macroscopic production xs member
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/dports/science/openmc/openmc-0.12.2/include/openmc/ |
H A D | xsdata.h | 81 xt::xtensor<double, 2> nu_fission; variable
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H A D | particle_data.h | 88 double nu_fission; //!< neutron production from fission member 141 double nu_fission; //!< macroscopic production xs member
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/dports/science/py-OpenMC/openmc-0.12.2/openmc/ |
H A D | mgxs_library.py | 325 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
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/dports/science/openmc/openmc-0.12.2/openmc/ |
H A D | mgxs_library.py | 325 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
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/dports/science/py-OpenMC/openmc-0.12.2/src/ |
H A D | mgxs.cpp | 555 double nu_fission = xs_t->nu_fission(cache[tid].a, gin); in sample_fission_energy() local
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/dports/science/openmc/openmc-0.12.2/src/ |
H A D | mgxs.cpp | 555 double nu_fission = xs_t->nu_fission(cache[tid].a, gin); in sample_fission_energy() local
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