Mcnp input files

External doses in humans from Cs in soil. Health Physics 91 3 : ; Conversion coefficients for age dependent ORNL phantoms from Cs in soil as a source of external exposure.

Nuclear Instruments and Methods A 1 ; Nature of problem: The human body and all organs are represented with equations of 3-D geometrical bodies. All equations and other relevant data material composition, densities etc. All organs of the human body were represented with analytical equations of various three dimensional geometrical bodies. Inequalities were also used to represent some organs. It is out of the scope of this work to give all equations and inequalities used for organs of human phantoms and only the most important characteristics are given here.

The ORNL phantom consisted of three sections: 1 the trunk and arms were represented as elliptical cylinders; 2 legs and feet were two truncated circular cones; and 3 the neck and head were represented with a circular cylinder on which another elliptical cylinder, covered by half of an ellipsoid was situated. Two ellipsoids representing the female breasts were attached to the trunk of the female phantom.

In addition to the geometrical shapes, the chemical constitution and densities of tissues of particular organs were needed for absorbed dose calculations. Three types of tissues, skeletal, lung and soft, with different densities and elemental compositions were present in ORNL phantoms. In this kind of geometric problem a suitable choice of coordinate system was very important and can significantly reduce the calculation time in some problems.

The coordinate origin was taken at the center of the lower base of the trunk section of the phantom. The z axis was directed vertically upward. The y axis and x axis were horizontally directed to the posterior side and towards the left hand side of the phantom, respectively. External shapes of organs were defined as planes, spheres, cylinders, cones, ellipsoids, elliptical cylinders, tori and combinations of these geometrical bodies. All equations and inequalities for organs of all phantoms, with other relevant information elemental compositions, volumes, masses etc , were programmed in input files for MCNP-4B code.

So far, 46 cells and surfaces were used for a male phantom in the input file. The length of the record can either be hard-coded by setting the number parameter e. Read the list of variable IDs that each record type in the Ptrac file is comprised of. The variables can vary for different problems. Consult the MCNP manual for details. Writes the events contained in this Ptrac file to a given HDF5 table. The table must already exist and have rows that match the PtracEvent definition.

Example use cases include adding source particles from other codes, and combining multiple files together. Note that typically additional code will be needed to supplement this class in order to modify the header or track information in a way suitable to the use case. Read in the header block data. This block comprises 4 fortran records which we refer to as: header, table1, table2, summary. Write the first part of the MCNP surface source file.

The header content comprises five parts shown below. Write track records for individual particles. Second part of the MCNP surface source file. Weight window lower bounds are stored on a structured mesh.

Note the origin is not considered a coarse mesh point as in MCNP. A three character string denoting the iteration order of the mesh e. This is a mapping of volume element handles to Material objects. If mats is None, then no empty materials are created for the mesh. Typically volume elements should be indexed from 0. This method creates a Wwinp object from a structured mesh object. Stores all information that describes a xsdir table entry, which appears as a single line in xsdir file.

If filetype is 1, address is the line number of the xsdir table. If filetype is 2, address is the record number. True if xs table describes continuous energy neutron data with unresolved resonance range probability tables.

Converts cross section table type to Serpent format: continuous energy c. This function reads an MCNP material card from a file and returns a Material or Multimaterial object for the material described by the card. A Material object is returned if there is 1 density supplied. If multiple densities are supplied a MultiMaterial is returned. This function reads an MCNP inp file and returns a mapping of material numbers to material objects. This function reads a structured Mesh object and returns the geometry portion of an MCNP input file cells, surfaces, materials , prepended by a title card.

The mesh must be axis aligned. Surfaces and cells are written in xyz iteration order z changing fastest.