MCNP Namespace Reference

This MCNP (concrete) class is used to built a reactor assembly. More...

Classes
class	Brick
	A 3D rectangular parallepipede Shape. More...
class	Connector
	Define a MCNP Connector. More...
class	Cylinder
	Infinite cylinder Shape. More...
class	GroupBin
	Define MCNP group a cell or surface bin. More...
class	Hexagon
	Regular hexagon Shape of a given height. More...
class	LatticeBin
	Define Lattice Cell type bin. More...
class	Node
	Node allows to construct Union or Intersection of Shape. More...
class	Plane
	Infinite plane Shape (or half space). More...
class	ReactorAssembly
class	SimpleBin
	Define a MCNP Simple Bin. More...
class	Sphere
	Define a Sphere Shape. More...
class	Tally
	Define a MCNP Tally. More...
class	TimeEnergyGrid
	Define a Time and/or Energy Grid for tallies. More...
class	Tube
	A Tube is a finite Cylinder with a hole inside (like a pipe). More...
class	ZTorus
	Define a ZTorus Shape. More...

Enumerations
enum	TallyType {   kSurfaceCurrent = 1 , kSurfaceFlux , kCellFlux = 4 , kEnergyDeposition = 6 ,   kFissionEnergyDeposition }
	Define tally type according to MCNP notation (1=Current/surf, 2=flux/surf, 4=flux/cell, ...) More...

Detailed Description

This MCNP (concrete) class is used to built a reactor assembly.

the namespace use to couple MURE and MCNP

Assemblies built with this class are basic cuboid or hexagonal VERTICAL assemblies that can be rotated by +/-Pi/2.

Assembly are filled with fuel pins, guide tubes and control rods. Each GenericReactorAssembly can be discretized in radial zones and axial levels either for evolution purpose, or for thermohydraulics (coupled or not with evolution) purposed. By default only 1 radial zone and 1 axial level is created. In each zone, all material of a given type of Pincell is the same (composition &temperature).

Data must be given in SI (dimensions in meters) All GenericReactorAssembly are created at (0, 0, 0) ; use GenericReactorAssembly::Translate to move it (before any call to GenericReactorAssembly::BuildAssemblyGeometry().

WARNING: Some methods must be called before others ; even if error messages are provided, read the user guide.

example:

Shape_ptr Ass(new Hexagon(H/2, Side));
Shape_ptr Exterior=!Ass;
 
ReactorAssembly *RA=new ReactorAssembly(Pitch, 3, 3);
 
RA->SetPlenum(0.1, Sodium);
 
RA->SetAssemblyShape(Ass);
 
RA->AddRadialZone2Mesh(R0, 0);
RA->AddRadialZone2Mesh(R1, 1;
RA->AddRadialZone2Mesh(R2, 2);
 
RA->AddFuelPin(AFuelPin);
 
RA->AddGuideTubePin(AGuideTubePin, -1, 2);
RA->AddGuideTubePin(AGuideTubePin, 0, 2);
RA->AddGuideTubePin(AGuideTubePin, 1, 2);
RA->AddGuideTubePin(AGuideTubePin, -1, -2);
RA->AddGuideTubePin(AGuideTubePin, 0, -2);
RA->AddGuideTubePin(AGuideTubePin, 1, -2);
 
RA->SetBorderPin(ASodiumPin);
 
RA->BuildAssemblyGeometry();
 
Cell *exterior=new Cell(Exterior, 0, 0);
 
gMURE->BuildMCFile("minp");

Author

Nico*

pto

Version

3.0

Enumeration Type Documentation

TallyType

enum MCNP::TallyType

Define tally type according to MCNP notation (1=Current/surf, 2=flux/surf, 4=flux/cell, ...)

Enumerator
kSurfaceCurrent
kSurfaceFlux
kCellFlux
kEnergyDeposition
kFissionEnergyDeposition