Data Cards in MCNP

Essential physics and calculation parameters

What Data Cards Control

Data cards tell MCNP how to handle the physics of your simulation. They control material properties, particle transport, calculation parameters, and output options. While geometry defines the physical structure, data cards define the behavior. This page covers physics control, execution, and output cards. For details on specific card types, see the dedicated pages on Materials, Tallies, Source Definitions, and Criticality Calculations.

Essential Data Card Categories

Materials (M, MT, TMP)

Composition and thermal properties

Physics (PHYS, CUT, MODE)

Transport and interaction controls

Problem Control (NPS, CTME, PRDMP)

Calculation execution parameters

Output (PRINT, PTRAC, DBCN)

Results and diagnostic options

Physics Control Cards

These cards control how MCNP handles particle transport and interactions. Getting these right is crucial for both accuracy and efficiency.

Basic Physics Setup

mcnp
c Particle transport modes
MODE  n p                 $ Transport neutrons and photons

c Physics parameters
PHYS:N  100  0  0  -1  -1  $ Neutron physics to 100 MeV
PHYS:P  100  0  1          $ Photon physics to 100 MeV

c Energy cutoffs
CUT:N   J  0.001           $ Default time, 1 keV energy cutoff
CUT:P   J  0.01            $ Default time, 10 keV energy cutoff

The MODE card specifies which particles to transport. PHYS cards control detailed physics options - the first parameter sets the maximum energy, while others control specific physics models. CUT cards set energy cutoffs below which particles are terminated, balancing accuracy with computational efficiency.

Specialized Physics Options

mcnp
c Criticality-specific controls
TOTNU    NO                $ Disable delayed neutrons
ACT      FISS=ALL         $ Track all fission products

c Variance reduction
IMP:N    1 1 0 2 4        $ Neutron importance by cell
IMP:P    1 1 0 2 4        $ Photon importance by cell
FCL:N    1 1 1            $ Force collisions in cells 1-3

TOTNU controls delayed neutron treatment in criticality calculations. IMP cards set importance values for variance reduction, while FCL forces collisions in specified cells for variance reduction.

Calculation Control

These cards control how long your calculation runs and how it terminates. They're essential for managing computational resources and ensuring reliable results.

Fixed Source Problems

mcnp
c Basic execution control
NPS    1e6                 $ Run 1 million particle histories
CTME   60                  $ Time limit: 60 minutes

c Statistical checks
DBCN   17J 1              $ Debug control card
PRDMP  2J  1  10          $ Write restart file every 10 batches

c Random number control
RAND   GEN=2  SEED=12345  $ Random number generator

NPS sets the number of particle histories to run. CTME provides a time limit as backup termination. DBCN provides debug diagnostics. PRDMP creates restart files for long calculations. RAND controls random number generation for reproducible results.

Criticality Problems

mcnp
c Criticality calculation setup
KCODE  10000  1.0  50  250    $ particles/cycle, k-guess, skip, total
KSRC   0 0 0               $ Initial source point
       10 0 0              $ Additional points for coverage

c Criticality-specific controls
KOPTS  BLOCKSIZE=10        $ Batch size for statistics
CTME   120                 $ Time limit: 2 hours
PRDMP  2J  1  25           $ Restart files every 25 cycles

KCODE specifies criticality parameters: particles per cycle, initial k-effective guess, cycles to skip for convergence, and total cycles. KSRC provides initial source locations. KOPTS controls advanced criticality options like batch sizes for improved statistics.

Output and Diagnostics

These cards control what information MCNP provides in its output files. They're essential for understanding your results and diagnosing problems.

Standard Output Control

mcnp
c Print table control
PRINT  30 40 50 110 126 -85 -86 -87  $ Print tables (negative suppresses)

c Particle tracking
PTRAC  BUFFER=1000  FILE=ptrac.txt  $ Particle trace file
       WRITE=POS,CEL,MAT,NPS       $ Track position, cell, material

c Performance monitoring
PRDMP  2J  1  50  1       $ Dump/restart file control

PRINT controls which tables appear in the output file. Positive numbers enable tables, negative numbers suppress them. PTRAC creates detailed particle tracking files for debugging. PRDMP controls restart file frequency.

Advanced Diagnostics

mcnp
c Detailed physics information
PHYS:N  100  0  0  -1  -1  J  $ Enable physics diagnostics
PHYS:P  100  0  1  0   0   J  $ Photon physics with details

c Cross-section information
PRINT  104                 $ Cross-section tables
c The XSDIR file location is set via the DATAPATH
c environment variable, not via an input card.

c Debug diagnostics
DBCN   17J 1               $ Extended diagnostics

In MCNP, 'J' means "jump" (use the default value for that parameter position). PRINT 104 shows cross-section information. The cross-section directory location is set via the DATAPATH environment variable. These options help diagnose physics modeling issues.

Material Temperature Effects

Temperature affects neutron cross-sections and scattering behavior. For accurate results, especially with thermal neutrons, you need to specify material temperatures.

mcnp
c Water at room temperature
m1    1001.80c  2.0        $ Hydrogen
      8016.80c  1.0        $ Oxygen
mt1   lwtr.10t             $ Thermal scattering data

c Fuel at operating temperature
m2    92235.80c  0.05      $ U-235
      92238.80c  0.95      $ U-238
      8016.80c   2.0       $ Oxygen

c Graphite moderator
m3    6000.80c  1.0        $ Carbon
mt3   grph.10t             $ Graphite thermal treatment

c Temperature card: one value per cell (kT in MeV)
c Assumes cells use materials 1, 2, 3 in order
TMP   2.5301e-8  6.6918e-8  8.6173e-8

The TMP card specifies cell temperatures in MeV (kT = K × 8.617e-11), listed in cell order (one value per cell). It is a cell property, not a material property. MT cards provide thermal scattering data for bound atoms in molecules or crystals. These effects are crucial for accurate thermal neutron transport in moderators.

Common Mistakes and Solutions

Avoiding Common Errors

Many MCNP problems stem from incorrect data card usage. Here are the most common issues and how to avoid them:

Missing MODE card

Always specify which particles to transport. Default is neutrons only.

Inappropriate energy cutoffs

Set CUT values based on your problem - too high loses accuracy, too low wastes time.

Insufficient statistics

Use DBCN to enable convergence checks and ensure adequate particle histories.

Wrong temperature units

TMP uses MeV, not Kelvin. Convert with: MeV = K × 8.617e-11.

Data Card Best Practices

Start with minimal data cards and add complexity as needed. Always include MODE, NPS, and appropriate physics cards. Use PRINT to control output verbosity - suppress unnecessary tables to keep output files manageable.

For criticality problems, ensure adequate source point coverage and sufficient inactive cycles for convergence. Monitor k-effective convergence and adjust parameters if needed. Document all non-default settings for reproducibility.