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Cleaning up code, resolving @paulromano comments
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cd1dfc0d19
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7 changed files with 27 additions and 59 deletions
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@ -11,9 +11,9 @@
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namespace openmc {
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typedef std::vector<std::vector<double> > double_2dvec;
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typedef std::vector<std::vector<std::vector<double> > > double_3dvec;
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typedef std::vector<std::vector<std::vector<std::vector<double> > > > double_4dvec;
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using double_2dvec = std::vector<std::vector<double>>;
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using double_3dvec = std::vector<std::vector<std::vector<double>>>;
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using double_4dvec = std::vector<std::vector<std::vector<std::vector<double>>>>;
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// ============================================================================
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// VERSIONING NUMBERS
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@ -70,9 +70,6 @@ void
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read_nd_vector(hid_t obj_id, const char* name, xt::xtensor<double, 4>& result,
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bool must_have = false);
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void
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read_nd_vector(hid_t obj_id, const char* name, xt::xtensor<double, 5>& result,
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bool must_have = false);
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std::vector<hsize_t> attribute_shape(hid_t obj_id, const char* name);
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std::vector<std::string> dataset_names(hid_t group_id);
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@ -159,7 +159,7 @@ class Mgxs {
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//! @param dg delayed group index; use nullptr if irrelevant.
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//! @return Requested cross section value.
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double
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get_xs(const int xstype, const int gin, int* gout, double* mu, int* dg);
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get_xs(int xstype, int gin, int* gout, double* mu, int* dg);
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//! \brief Samples the fission neutron energy and if prompt or delayed.
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//!
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@ -167,7 +167,7 @@ class Mgxs {
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//! @param dg Sampled delayed group index.
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//! @param gout Sampled outgoing energy group.
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void
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sample_fission_energy(const int gin, int& dg, int& gout);
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sample_fission_energy(int gin, int& dg, int& gout);
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//! \brief Samples the outgoing energy and angle from a scatter event.
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//!
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@ -176,7 +176,7 @@ class Mgxs {
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//! @param mu Sampled cosine of the change-in-angle.
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//! @param wgt Weight of the particle to be adjusted.
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void
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sample_scatter(const int gin, int& gout, double& mu, double& wgt);
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sample_scatter(int gin, int& gout, double& mu, double& wgt);
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//! \brief Calculates cross section quantities needed for tracking.
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//!
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@ -187,14 +187,14 @@ class Mgxs {
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//! @param abs_xs Resultant absorption cross section.
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//! @param nu_fiss_xs Resultant nu-fission cross section.
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void
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calculate_xs(const int gin, const double sqrtkT, const double uvw[3],
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calculate_xs(int gin, double sqrtkT, const double uvw[3],
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double& total_xs, double& abs_xs, double& nu_fiss_xs);
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//! \brief Sets the temperature index in cache given a temperature
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//!
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//! @param sqrtkT Temperature of the material.
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void
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set_temperature_index(const double sqrtkT);
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set_temperature_index(double sqrtkT);
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//! \brief Sets the angle index in cache given a direction
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//!
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@ -94,7 +94,7 @@ class XsData {
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// [angle][incoming group][outgoing group][delayed group]
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xt::xtensor<double, 4> chi_delayed;
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// scatter has the following dimensions: [angle]
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std::vector<std::shared_ptr<ScattData> > scatter;
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std::vector<std::shared_ptr<ScattData>> scatter;
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XsData() = default;
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