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MCNP and MCNPX Data Items
Moritz reads and writes MCNP data items (input other than cell and surface definitions). Data items specific to MCNPX, except for the mesh tally, are ignored. Except for transformations (TR), superimposed mesh, mesh tally data, and some material data, the data cannot yet be created or edited in Moritz. We plan to implement this capability soon. Some data types are parsed directly and stored in program memory. For other data types, the input lines are simply copied.
The input types that are parsed are C, DE, DF, DS, E, F, FQ, FS, IMP, KCODE, KSRC, MESH, FMESH, M, MGOPT, NONU, PHYS, PRDMP, PRINT, SDEF, SI, SP, SB, SD, T, THTME, TR, VECT, VOID, WWE, WWG, and WWGE. The tally number is read from tally data types not listed above. The MCNPX TMESH block is also parsed. The special syntax items I (interpolate), J (jump), R (repeat), and M (multiply) are recognized. Except for J, the expanded values are stored and memory of the special syntax is lost. For example, “4 2R” encountered on input will be written as “4 4 4” when an input file is generated. A single preceding comment line is remembered for DE, DF, and TR. Up to 10 comments after the last preceding noncomment line are remembered for F and SDEF.
Parsing data input was introduced in Moritz Version 0.89. We have not yet had the opportunity to test all possible variations of the parsed data types. It is possible that some unexpected syntax variations could lead to problems. If problems occur, first disable reading data items by checking Read No Data on the Input property page (invoked from the File menu). Individual data types can be selected for reading or not on the MCNP Data dialog (invoked from the Input property page).
The parsed data items are written in the order in which they appear in the MCNP4c manual. Unparsed tally lines are written following other data for each tally. Other unparsed data is written at the end of the data block in the order they were read.
We are aware of some limitations (that we will address in future versions). The direction option for F5 tallies is not remembered: F5Y:n on input is written as F5:n. Tally references to lattice elements is incorrect: (1 < 10[-1 1 0]) on input is written as (1 101 1 0). Multiple particle designators such as IMP:p,e confuse the parser and lead to an error. Numbers in scientific notation but lacking an E, such as 3.96-6 rather than 3.96e-6, are not read correctly and produce an error message.
 White Rock Science http://www.whiterockscience.com/wrs.html 505 672 1105 |
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