Difference between revisions of "Input syntax manual"
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*Neutron external source simulations are limited to sub-critical systems, unless time cut-off ([[#set tcut|set tcut]]) or generation cut-off ([[#set gcut|set gcut]]) is invoked. | *Neutron external source simulations are limited to sub-critical systems, unless time cut-off ([[#set tcut|set tcut]]) or generation cut-off ([[#set gcut|set gcut]]) is invoked. | ||
*Neutron external source simulations in multiplying systems may require adjusting the neutron buffer ([[#set nbuf|set nbuf]]). | *Neutron external source simulations in multiplying systems may require adjusting the neutron buffer ([[#set nbuf|set nbuf]]). | ||
| − | + | *Delayed neutron emission is switched off by default in neutron external source simulation (for compatibility with MCNP). Delayed neutrons can be included with [[#set delnu|set delnu]. | |
=== set pop === | === set pop === | ||
Revision as of 18:01, 17 November 2015
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 gcut
set gcut <ng>
Sets generation cut-off for neutrons. Input values:
| <ng> | number of simulated generations before cut-off |
The cut-off can be used in neutron external source simulations, to limit the length of fission chains.
Notes:
- Applicable only to neutron external source simulation (invoked using (set nps)
- Generation or time cut-off (set tcut) is needed for external source simulations in super-critical systems
set nps
set nps <ppb> [ <btch> ]
Sets parameters for simulated particle population in external source mode. Input values:
| <ppb> | number of particles per batch |
| <btch> | number of batches |
The simulation is for a number batches using the given batch size.
Notes:
- Using the nps card sets the mode to external source simulation. Criticality source simulation for neutrons is invoked using set pop.
- Running an external source simulation requires a source, defined by the src card. Source definition also sets the transported particle type.
- Neutron external source simulations are limited to sub-critical systems, unless time cut-off (set tcut) or generation cut-off (set gcut) is invoked.
- Neutron external source simulations in multiplying systems may require adjusting the neutron buffer (set nbuf).
- Delayed neutron emission is switched off by default in neutron external source simulation (for compatibility with MCNP). Delayed neutrons can be included with [[#set delnu|set delnu].
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.
References
- ^ Leppänen, J. "Development of a new Monte Carlo reactor physics code." D.Sc. Thesis, Helsinki University of Technology, 2007. (VTT Publications 640)
