Input syntax manual
Contents
Preface
This page will contain the whole input syntax of Serpent 2
This is a reference to one article [1]
This is another reference to the same article [1]
Input cards
mat (material definition)
surf (surface definition)
cell (cell definition)
det (detector definition)
src
Input options
set pop
set pop <npg> <ngen> <nskip> [ <keff0> <btch> ]
Sets parameters for simulated neutron population in criticality source mode. Input values:
| <npg> | number of neutrons per generation |
| <ncyc> | number of active generations |
| <nskip> | number of inactive generations |
| <keff0> | initial guess for k-eff |
| <btch> | batching interval |
The simulation is first run for a number of inactive generations to allow the fission source to converge. This is followed by a number of active generations, during which the results are collected. The statistics are divided in batches, and by default each generation forms its own batch.
Notes:
- Using the pop card sets the mode to criticality source simulation. External source simulation is invoked using #set nps.
- Convergence of fission source can be monitored using Shannon entropy (input parameters set his and set entr).
- See detailed description on the statistical effects of batching.
set nps
set nps <npg> [<keff0> <>]
Setting the neutron population.
| <npg> | neutrons_per_generation |
| <nc> | neutrons |
set delnu
set roulette
References
- ^ Leppänen, J. "Development of a new Monte Carlo reactor physics code." D.Sc. Thesis, Helsinki University of Technology, 2007. (VTT Publications 640)
