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Remove Material p0 and element attributes on Fortran side

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This commit is contained in:
Paul Romano 2019-01-25 11:17:03 -06:00
parent 08d55249ae
commit f407982ff6
5 changed files with 25 additions and 122 deletions
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include/openmc/material.h
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@ -73,7 +73,6 @@ public:
double volume_ {-1.0}; //!< Volume in [cm^3]
bool fissionable_ {false}; //!< Does this material contain fissionable nuclides
bool depletable_ {false}; //!< Is the material depletable?
bool has_isotropic_nuclides_ {false};
std::vector<bool> p0_; //!< Indicate which nuclides are to be treated with iso-in-lab scattering
// Thermal scattering tables