Difference between revisions of "Input syntax manual"
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<nowiki>set delnu <dnu></nowiki>
<nowiki>set delnu <dnu></nowiki>
Sets delayed neutron emission on or off Input values:
Sets delayed neutron emission on or offInput values:
Revision as of 18:11, 17 November 2015
This page will contain the whole input syntax of Serpent 2
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mat (material definition)
surf (surface definition)
cell (cell definition)
det (detector definition)
set delnu <dnu>
Sets delayed neutron emission on or off. Input values:
|<dnu>||option to switch delayed neutron emission off (0/no) or on (1/yes)|
- Delayed neutron emission is on by default in neutron criticality source and off by default in external source simulations.
set gcut <gmax>
Sets generation cut-off for neutrons. Input values:
|<gmax>||number of simulated generations before cut-off|
The generation cut-off can be used in neutron external source simulations, to limit the length of fission chains.
- Applicable only to neutron external source simulation (invoked using (set nps)
- Generation or time cut-off (set tcut) is always needed for neutron external source simulations in super-critical systems.
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.
- 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 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|
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.
- 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 tcut <tmax>
Sets time cut-off for neutrons and photons. Input values:
|<tmax>||time limit for simulated particle histories (in seconds)|
The time cut-off can be used in both neutron and photon external source simulations, to limit the length of particle histories.
- Time or generation cut-off (set gcut) is always needed for neutron external source simulations in super-critical systems.
- Note to developers: this should take independent values for photons and neutrons