16033007652

Committed 02 Jul 2025 06:33PM UTC coverage: 85.251% (-0.08%) from 85.33%

Build # 16033007652

Build Type

Pull #3484

github

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web-flow

Commit Message

Merge ffaa13385 into eb74d497d

Pull Request Pull Request #3484: fix zam parsing

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33.33

/include/openmc/material.h

#ifndef OPENMC_MATERIAL_H
#define OPENMC_MATERIAL_H

#include <string>
#include <unordered_map>

#include "openmc/span.h"
#include "pugixml.hpp"
#include "xtensor/xtensor.hpp"
#include <hdf5.h>

#include "openmc/bremsstrahlung.h"
#include "openmc/constants.h"
#include "openmc/memory.h" // for unique_ptr
#include "openmc/ncrystal_interface.h"
#include "openmc/particle.h"
#include "openmc/vector.h"

namespace openmc {

//==============================================================================
// Global variables
//==============================================================================

class Material;

namespace model {

extern std::unordered_map<int32_t, int32_t> material_map;
extern vector<unique_ptr<Material>> materials;

} // namespace model

//==============================================================================
//! A substance with constituent nuclides and thermal scattering data
//==============================================================================

class Material {
public:
  //----------------------------------------------------------------------------
  // Types
  struct ThermalTable {
    int index_table;   //!< Index of table in data::thermal_scatt
    int index_nuclide; //!< Index in nuclide_
    double fraction;   //!< How often to use table
  };

  //----------------------------------------------------------------------------
  // Constructors, destructors, factory functions
  Material() {};
  explicit Material(pugi::xml_node material_node);
  ~Material();

  //----------------------------------------------------------------------------
  // Methods

  void calculate_xs(Particle& p) const;

  //! Assign thermal scattering tables to specific nuclides within the material
  //! so the code knows when to apply bound thermal scattering data
  void init_thermal();

  //! Set up mapping between global nuclides vector and indices in nuclide_
  void init_nuclide_index();

  //! Finalize the material, assigning tables, normalize density, etc.
  void finalize();

  //! Write material data to HDF5
  void to_hdf5(hid_t group) const;

  //! Export physical properties to HDF5
  //! \param[in] group  HDF5 group to write to
  void export_properties_hdf5(hid_t group) const;

  //! Import physical properties from HDF5
  //! \param[in] group  HDF5 group to read from
  void import_properties_hdf5(hid_t group);

  //! Add nuclide to the material
  //
  //! \param[in] nuclide Name of the nuclide
  //! \param[in] density Density of the nuclide in [atom/b-cm]
  void add_nuclide(const std::string& nuclide, double density);

  //! Set atom densities for the material
  //
  //! \param[in] name Name of each nuclide
  //! \param[in] density Density of each nuclide in [atom/b-cm]
  void set_densities(
    const vector<std::string>& name, const vector<double>& density);

  //! Clone the material by deep-copying all members, except for the ID,
  //  which will get auto-assigned to the next available ID. After creating
  //  the new material, it is added to openmc::model::materials.
  //! \return reference to the cloned material
  Material& clone();

  //----------------------------------------------------------------------------
  // Accessors

  //! Get density in [atom/b-cm]
  //! \return Density in [atom/b-cm]
  double density() const { return density_; }

  //! Get density in [g/cm^3]
  //! \return Density in [g/cm^3]
  double density_gpcc() const { return density_gpcc_; }

  //! Get charge density in [e/b-cm]
  //! \return Charge density in [e/b-cm]
  double charge_density() const { return charge_density_; };

  //! Get name
  //! \return Material name
  const std::string& name() const { return name_; }

  //! Set name
  void set_name(const std::string& name) { name_ = name; }

  //! Set total density of the material
  //
  //! \param[in] density Density value
  //! \param[in] units Units of density
  void set_density(double density, const std::string& units);

  //! Set temperature of the material
  void set_temperature(double temperature) { temperature_ = temperature; };

  //! Get nuclides in material
  //! \return Indices into the global nuclides vector
  span<const int> nuclides() const
  {
    return {nuclide_.data(), nuclide_.size()};
  }

  //! Get densities of each nuclide in material
  //! \return Densities in [atom/b-cm]
  span<const double> densities() const
  {
    return {atom_density_.data(), atom_density_.size()};
  }

  //! Get ID of material
  //! \return ID of material
  int32_t id() const { return id_; }

  //! Assign a unique ID to the material
  //! \param[in] Unique ID to assign. A value of -1 indicates that an ID
  //!   should be automatically assigned.
  void set_id(int32_t id);

  //! Get whether material is fissionable
  //! \return Whether material is fissionable
  bool fissionable() const { return fissionable_; }
  bool& fissionable() { return fissionable_; }

  //! Get volume of material
  //! \return Volume in [cm^3]
  double volume() const;

  //! Get temperature of material
  //! \return Temperature in [K]
  double temperature() const;

  //! Whether or not the material is depletable
  bool depletable() const { return depletable_; }
  bool& depletable() { return depletable_; }

  //! Get pointer to NCrystal material object
  //! \return Pointer to NCrystal material object
  const NCrystalMat& ncrystal_mat() const { return ncrystal_mat_; };

  //----------------------------------------------------------------------------
  // Data
  int32_t id_ {C_NONE};                 //!< Unique ID
  std::string name_;                    //!< Name of material
  vector<int> nuclide_;                 //!< Indices in nuclides vector
  vector<int> element_;                 //!< Indices in elements vector
  NCrystalMat ncrystal_mat_;            //!< NCrystal material object
  xt::xtensor<double, 1> atom_density_; //!< Nuclide atom density in [atom/b-cm]
  double density_;                      //!< Total atom density in [atom/b-cm]
  double density_gpcc_;                 //!< Total atom density in [g/cm^3]
  double charge_density_;               //!< Total charge density in [e/b-cm]
  double volume_ {-1.0};                //!< Volume in [cm^3]
  vector<bool> p0_; //!< Indicate which nuclides are to be treated with
                    //!< iso-in-lab scattering

  // To improve performance of tallying, we store an array (direct address
  // table) that indicates for each nuclide in data::nuclides the index of the
  // corresponding nuclide in the nuclide_ vector. If it is not present in the
  // material, the entry is set to -1.
  vector<int> mat_nuclide_index_;

  // Thermal scattering tables
  vector<ThermalTable> thermal_tables_;

  unique_ptr<Bremsstrahlung> ttb_;

private:
  //----------------------------------------------------------------------------
  // Private methods

  //! Calculate the collision stopping power
  void collision_stopping_power(double* s_col, bool positron);

  //! Initialize bremsstrahlung data
  void init_bremsstrahlung();

  //! Normalize density
  void normalize_density();

  void calculate_neutron_xs(Particle& p) const;
  void calculate_photon_xs(Particle& p) const;

  //----------------------------------------------------------------------------
  // Private data members
  int64_t index_;

  bool depletable_ {false}; //!< Is the material depletable?
  bool fissionable_ {
    false}; //!< Does this material contain fissionable nuclides
  //! \brief Default temperature for cells containing this material.
  //!
  //! A negative value indicates no default temperature was specified.
  double temperature_ {-1};
};

//==============================================================================
// Non-member functions
//==============================================================================

//! Calculate Sternheimer adjustment factor
double sternheimer_adjustment(const vector<double>& f,
  const vector<double>& e_b_sq, double e_p_sq, double n_conduction,
  double log_I, double tol, int max_iter);

//! Calculate density effect correction
double density_effect(const vector<double>& f, const vector<double>& e_b_sq,
  double e_p_sq, double n_conduction, double rho, double E, double tol,
  int max_iter);

//! Read material data from materials.xml
void read_materials_xml();

//! Read material data XML node
//! \param[in] root node of materials XML element
void read_materials_xml(pugi::xml_node root);

void free_memory_material();

} // namespace openmc
#endif // OPENMC_MATERIAL_H

1	#ifndef OPENMC_MATERIAL_H
2	#define OPENMC_MATERIAL_H
3
4	#include <string>
5	#include <unordered_map>
6
7	#include "openmc/span.h"
8	#include "pugixml.hpp"
9	#include "xtensor/xtensor.hpp"
10	#include <hdf5.h>
11
12	#include "openmc/bremsstrahlung.h"
13	#include "openmc/constants.h"
14	#include "openmc/memory.h" // for unique_ptr
15	#include "openmc/ncrystal_interface.h"
16	#include "openmc/particle.h"
17	#include "openmc/vector.h"
18
19	namespace openmc {
20
21	//==============================================================================
22	// Global variables
23	//==============================================================================
24
25	class Material;
26
27	namespace model {
28
29	extern std::unordered_map<int32_t, int32_t> material_map;
30	extern vector<unique_ptr<Material>> materials;
31
32	} // namespace model
33
34	//==============================================================================
35	//! A substance with constituent nuclides and thermal scattering data
36	//==============================================================================
37
38	class Material {
39	public:
40	//----------------------------------------------------------------------------
41	// Types
42	struct ThermalTable {
43	int index_table; //!< Index of table in data::thermal_scatt
44	int index_nuclide; //!< Index in nuclide_
45	double fraction; //!< How often to use table
46	};
47
48	//----------------------------------------------------------------------------
49	// Constructors, destructors, factory functions
50	Material() {};
51	explicit Material(pugi::xml_node material_node);
52	~Material();
53
54	//----------------------------------------------------------------------------
55	// Methods
56
57	void calculate_xs(Particle& p) const;
58
59	//! Assign thermal scattering tables to specific nuclides within the material
60	//! so the code knows when to apply bound thermal scattering data
61	void init_thermal();
62
63	//! Set up mapping between global nuclides vector and indices in nuclide_
64	void init_nuclide_index();
65
66	//! Finalize the material, assigning tables, normalize density, etc.
67	void finalize();
68
69	//! Write material data to HDF5
70	void to_hdf5(hid_t group) const;
71
72	//! Export physical properties to HDF5
73	//! \param[in] group HDF5 group to write to
74	void export_properties_hdf5(hid_t group) const;
75
76	//! Import physical properties from HDF5
77	//! \param[in] group HDF5 group to read from
78	void import_properties_hdf5(hid_t group);
79
80	//! Add nuclide to the material
81	//
82	//! \param[in] nuclide Name of the nuclide
83	//! \param[in] density Density of the nuclide in [atom/b-cm]
84	void add_nuclide(const std::string& nuclide, double density);
85
86	//! Set atom densities for the material
87	//
88	//! \param[in] name Name of each nuclide
89	//! \param[in] density Density of each nuclide in [atom/b-cm]
90	void set_densities(
91	const vector<std::string>& name, const vector<double>& density);
92
93	//! Clone the material by deep-copying all members, except for the ID,
94	// which will get auto-assigned to the next available ID. After creating
95	// the new material, it is added to openmc::model::materials.
96	//! \return reference to the cloned material
97	Material& clone();
98
99	//----------------------------------------------------------------------------
100	// Accessors
101
102	//! Get density in [atom/b-cm]
103	//! \return Density in [atom/b-cm]
104	double density() const { return density_; }
105
106	//! Get density in [g/cm^3]
107	//! \return Density in [g/cm^3]
108	double density_gpcc() const { return density_gpcc_; }
109
110	//! Get charge density in [e/b-cm]
111	//! \return Charge density in [e/b-cm]
112	double charge_density() const { return charge_density_; };	1,065,482✔
113
114	//! Get name
115	//! \return Material name
116	const std::string& name() const { return name_; }
117
118	//! Set name
119	void set_name(const std::string& name) { name_ = name; }
120
121	//! Set total density of the material
122	//
123	//! \param[in] density Density value
124	//! \param[in] units Units of density
125	void set_density(double density, const std::string& units);
126
127	//! Set temperature of the material
128	void set_temperature(double temperature) { temperature_ = temperature; };
129
130	//! Get nuclides in material
131	//! \return Indices into the global nuclides vector
132	span<const int> nuclides() const
133	{
134	return {nuclide_.data(), nuclide_.size()};
135	}
136
137	//! Get densities of each nuclide in material
138	//! \return Densities in [atom/b-cm]
139	span<const double> densities() const
140	{
141	return {atom_density_.data(), atom_density_.size()};
142	}
143
144	//! Get ID of material
145	//! \return ID of material
UNCOV 146	int32_t id() const { return id_; }	×
147
148	//! Assign a unique ID to the material
149	//! \param[in] Unique ID to assign. A value of -1 indicates that an ID
150	//! should be automatically assigned.
151	void set_id(int32_t id);
152
153	//! Get whether material is fissionable
154	//! \return Whether material is fissionable
155	bool fissionable() const { return fissionable_; }
156	bool& fissionable() { return fissionable_; }	×
157
158	//! Get volume of material
159	//! \return Volume in [cm^3]
160	double volume() const;
161
162	//! Get temperature of material
163	//! \return Temperature in [K]
164	double temperature() const;
165
166	//! Whether or not the material is depletable
167	bool depletable() const { return depletable_; }
168	bool& depletable() { return depletable_; }
169
170	//! Get pointer to NCrystal material object
171	//! \return Pointer to NCrystal material object
172	const NCrystalMat& ncrystal_mat() const { return ncrystal_mat_; };
173
174	//----------------------------------------------------------------------------
175	// Data
176	int32_t id_ {C_NONE}; //!< Unique ID
177	std::string name_; //!< Name of material
178	vector<int> nuclide_; //!< Indices in nuclides vector
179	vector<int> element_; //!< Indices in elements vector
180	NCrystalMat ncrystal_mat_; //!< NCrystal material object
181	xt::xtensor<double, 1> atom_density_; //!< Nuclide atom density in [atom/b-cm]
182	double density_; //!< Total atom density in [atom/b-cm]
183	double density_gpcc_; //!< Total atom density in [g/cm^3]
184	double charge_density_; //!< Total charge density in [e/b-cm]
185	double volume_ {-1.0}; //!< Volume in [cm^3]
186	vector<bool> p0_; //!< Indicate which nuclides are to be treated with
187	//!< iso-in-lab scattering
188
189	// To improve performance of tallying, we store an array (direct address
190	// table) that indicates for each nuclide in data::nuclides the index of the
191	// corresponding nuclide in the nuclide_ vector. If it is not present in the
192	// material, the entry is set to -1.
193	vector<int> mat_nuclide_index_;
194
195	// Thermal scattering tables
196	vector<ThermalTable> thermal_tables_;
197
198	unique_ptr<Bremsstrahlung> ttb_;
199
200	private:
201	//----------------------------------------------------------------------------
202	// Private methods
203
204	//! Calculate the collision stopping power
205	void collision_stopping_power(double* s_col, bool positron);
206
207	//! Initialize bremsstrahlung data
208	void init_bremsstrahlung();
209
210	//! Normalize density
211	void normalize_density();
212
213	void calculate_neutron_xs(Particle& p) const;
214	void calculate_photon_xs(Particle& p) const;
215
216	//----------------------------------------------------------------------------
217	// Private data members
218	int64_t index_;
219
220	bool depletable_ {false}; //!< Is the material depletable?
221	bool fissionable_ {
222	false}; //!< Does this material contain fissionable nuclides
223	//! \brief Default temperature for cells containing this material.
224	//!
225	//! A negative value indicates no default temperature was specified.
226	double temperature_ {-1};
227	};
228
229	//==============================================================================
230	// Non-member functions
231	//==============================================================================
232
233	//! Calculate Sternheimer adjustment factor
234	double sternheimer_adjustment(const vector<double>& f,
235	const vector<double>& e_b_sq, double e_p_sq, double n_conduction,
236	double log_I, double tol, int max_iter);
237
238	//! Calculate density effect correction
239	double density_effect(const vector<double>& f, const vector<double>& e_b_sq,
240	double e_p_sq, double n_conduction, double rho, double E, double tol,
241	int max_iter);
242
243	//! Read material data from materials.xml
244	void read_materials_xml();
245
246	//! Read material data XML node
247	//! \param[in] root node of materials XML element
248	void read_materials_xml(pugi::xml_node root);
249
250	void free_memory_material();
251
252	} // namespace openmc
253	#endif // OPENMC_MATERIAL_H

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