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.

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   2J  0.001          $ 1 keV neutron cutoff
CUT:P   2J  0.01           $ 10 keV photon 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
NONU     40               $ No fission in cell 40
ACT      FISS 92235.80c   $ Activation tracking

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            $ Track light ion production

TOTNU controls delayed neutron treatment in criticality calculations. NONU prevents fission in specific cells. ACT enables activation tracking for specific isotopes. IMP cards set importance values for variance reduction, while FCL tracks secondary particle production.

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   0 0 0 1 2J 1       $ Enable all statistical checks
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 enables statistical checks to ensure convergence. 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    $ Selected print tables
PRINT  -85 -86 -87        $ Suppress verbose tables

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

c Performance monitoring
MPLOT  FREQ=100           $ Plot k-effective every 100 cycles
PRDMP  2J  1  50  1       $ Detailed dump files

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. MPLOT provides real-time monitoring of criticality calculations.

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
XSDIR  /path/to/xsdir      $ Cross-section directory

c Memory and performance
MPLOT  FREQ=50  TALLY=4    $ Monitor specific tally
DBCN   17 0 0 1 2J 1       $ Extended diagnostics

Adding 'J' to PHYS cards enables detailed physics diagnostics. PRINT 104 shows cross-section information. XSDIR specifies the location of nuclear data files. These options help diagnose physics modeling issues and verify correct data usage.

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
tmp1  2.5301e-8           $ Temperature (293.6 K)

c Fuel at operating temperature
m2    92235.80c  0.05      $ U-235
      92238.80c  0.95      $ U-238
      8016.80c   2.0       $ Oxygen
tmp2  6.6918e-8           $ Temperature (777 K)

c Graphite moderator
m3    6000.80c  1.0        $ Carbon
mt3   grph.10t             $ Graphite thermal treatment
tmp3  8.6173e-8           $ Temperature (1000 K)

The TMP card specifies material temperature in MeV (multiply Kelvin by 8.617e-11). 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.