Go to the source code of this file.
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class | Material |
| The Material class represents a unique material and its relevant nuclear data (i.e., multigroup cross-sections) for neutron transport. More...
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#define | MM_MALLOC(size, alignment) memalign(alignment, size) |
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#define | MM_FREE(array) free(array) |
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- Date
- January 19, 2012
- Author
- William Boyd, MIT, Course 22 (wboyd.nosp@m.@mit.nosp@m..edu)
◆ MM_FREE
#define MM_FREE |
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array | ) |
free(array) |
Aligned memory deallocation for GNU's compiler
◆ MM_MALLOC
#define MM_MALLOC |
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size, |
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alignment |
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| memalign(alignment, size) |
Aligned memory allocation for GNU's compiler
◆ material_id()
Returns an auto-generated unique Material ID.
This method is intended as a utility method for user's writing OpenMOC input files. The method makes use of a static Material ID which is incremented each time the method is called to enable unique generation of monotonically increasing IDs. The method's first ID begins at 1,000,000. Hence, user-defined material IDs greater than or equal to 1,000,000 is prohibited.
◆ maximize_material_id()
void maximize_material_id |
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int |
material_id | ) |
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Maximize the auto-generated unique Material ID counter.
This method updates the auto-generated unique Material ID counter if the input parameter is greater than the present value. This is useful for the OpenMC compatibility module to ensure that the auto-generated Material IDs do not collide with those created in OpenMC.
- Parameters
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material_id | the id assigned to the auto-generated counter |