A monte carlo pin cell spectral code for nuclear engineering applications.
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Neutron.h
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1 
10 #ifndef NEUTRON_H_
11 #define NEUTRON_H_
12 
13 class Region;
14 class Material;
15 class Isotope;
16 class Surface;
17 
27 struct neutron {
28 public:
29  /***************************************************************************
30  * ATTRIBUTES FOR INFINITE_MEDIUM AND HOMOGENEOUS_EQUIVALENCE GEOMETRIES *
31  **************************************************************************/
34 
36  float _energy;
37 
39  float _old_energy;
40 
42  bool _collided;
43 
46  // float _total_xs;
47 
49  float _path_length;
50 
52  bool _alive;
53 
56 
61 
65 
66 
67  /***************************************************************************
68  ***************** ATTRIBUTES FOR HETEROGENEOUS GEOMETRIES ***************
69  **************************************************************************/
72 
74  float _x;
75 
77  float _y;
78 
80  float _z;
81 
83  float _u;
84 
86  float _v;
87 
89  float _w;
90 
94  // float _mu;
95 
98  // float _phi;
99 };
100 
101 
103 
104 
105 #endif /* NEUTRON_H_ */
Represents a neutron in a PINSPEC simulation.
Definition: Neutron.h:27
Isotope * _isotope
Definition: Neutron.h:64
bool _alive
Definition: Neutron.h:52
The Surface represents a quadratic surface in the xy-plane.
Definition: Surface.h:73
The Isotope represents a nuclide at some temperature.
Definition: Isotope.h:41
int _batch_num
Definition: Neutron.h:33
float _z
Definition: Neutron.h:80
float _energy
Definition: Neutron.h:36
The region class represents a region in 2D space.
Definition: Region.h:58
float _x
Definition: Neutron.h:74
Region * _region
Definition: Neutron.h:55
float _y
Definition: Neutron.h:77
float _v
Definition: Neutron.h:86
float _w
Definition: Neutron.h:89
The Material class represents a collection of isotope objects.
Definition: Material.h:37
float _old_energy
Definition: Neutron.h:39
float _u
Definition: Neutron.h:83
float _path_length
Definition: Neutron.h:49
neutron * createNewNeutron()
Create a new empty neutron struct.
Definition: Neutron.cpp:7
Surface * _surface
Definition: Neutron.h:71
Material * _material
Definition: Neutron.h:60
bool _collided
Definition: Neutron.h:42