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match openmc style

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This commit is contained in:
Gavin Ridley 2019-11-07 14:01:04 -05:00
parent bdea083a0a
commit 8e1de2a577
4 changed files with 19 additions and 19 deletions
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12
include/openmc/mgxs_interface.h
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@ -45,8 +45,8 @@ struct MgxsInterface
MgxsInterface(const std::string& path_cross_sections,
const std::vector<std::string> xs_to_read,
const std::vector<std::vector<double>> xs_temps);
void setNuclidesToRead(std::vector<std::string> arg_xs_to_read);
void setNuclideTemperaturesToRead(std::vector<std::vector<double>> xs_temps);
void set_nuclides_to_read(std::vector<std::string> arg_xs_to_read);
void set_nuclide_temperatures_to_read(std::vector<std::vector<double>> xs_temps);
void init();
@ -59,7 +59,7 @@ struct MgxsInterface
// Reads just the header of the cross sections file, to find
// min & max energies as well as the available XS
void readHeader(const std::string& path_cross_sections);
void read_header(const std::string& path_cross_sections);
};
namespace data {
@ -69,14 +69,14 @@ namespace data {
// Puts available XS in MGXS file to globals so that when
// materials are read, the MGXS specified in a material can
// be ensured to be present in the available data.
void putMgxsHeaderDataToGlobals();
void put_mgxs_header_data_to_globals();
// Set which nuclides and temperatures are to be read on
// mgInterface through global data
void setMgInterfaceNuclidesAndTemps();
void set_mg_interface_nuclides_and_temps();
// After macro XS have been read, materials can be marked as fissionable
void markFissionableMgxsMaterials();
void mark_fissionable_mgxs_materials();
//==============================================================================
// Mgxs tracking/transport/tallying interface methods