Editing Input syntax manual (section)

=== set fmtx ===

 '''set fmtx''' '''1''' ''MAT<sub>1</sub>'' ''MAT<sub>2</sub>'' ...

 '''set fmtx''' '''2''' ''UNI<sub>1</sub>'' ''UNI<sub>2</sub>'' ...

 '''set fmtx''' '''3''' ''LVL''

 '''set fmtx''' '''4''' ''X<sub>MIN</sub>'' ''X<sub>MAX</sub>'' ''N<sub>X</sub>'' ''Y<sub>MIN</sub>'' ''Y<sub>MAX</sub>'' ''N<sub>Y</sub>'' ''Z<sub>MIN</sub>'' ''Z<sub>MAX</sub>'' ''N<sub>Z</sub>''

Set the calculation of fission matrixes. Input values:

{|
| <tt>''MAT<sub>n</sub>''</tt>
| : material list
|-
| <tt>''UNI<sub>n</sub>''</tt>
| : universe list
|-
| <tt>''LVL''</tt>
| : level number
|-
| <tt>''X<sub>MIN</sub>''</tt>
| : minimum x-coordinate mesh boundary [in cm]
|-
| <tt>''X<sub>MAX</sub>''</tt>
| : maximum x-coordinate mesh boundary [in cm]
|-
| <tt>''N<sub>X</sub>''</tt>
| : number of x-mesh cells 
|-
| <tt>''Y<sub>MIN</sub>''</tt>
| : minimum y-coordinate mesh boundary [in cm]
|-
| <tt>''Y<sub>MAX</sub>''</tt>
| : maximum y-coordinate mesh boundary [in cm]
|-
| <tt>''N<sub>Y</sub>''</tt>
| : number of y-mesh cells
|-
| <tt>''Z<sub>MIN</sub>''</tt>
| : minimum z-coordinate mesh boundary [in cm]
|-
| <tt>''Z<sub>MAX</sub>''</tt>
| : maximum z-coordinate mesh boundary [in cm]
|-
| <tt>''N<sub>Z</sub>''</tt>
| : number of z-mesh cells
|}

<u>Notes:</u>
* There are four options for defining the regions that compose the matrix: 1 = material, 2 = universe, 3 = level, 4 = Cartesian mesh.
* Output values are given in pairs: matrix element and associated relative error, for total, prompt and delayed (analog) fission matrixes.
* The output is printed in file <tt>[input]_fmtx[bu].m</tt>, where "<tt>bu</tt>" is the burnup step.