Difference between revisions of "Infinite homogeneous LWR-like reactor transient example"

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(Generating the steady state source distributions)
(Time dependent simulation (no reactivity insertion))
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== Time dependent simulation (no reactivity insertion) ==
 
== Time dependent simulation (no reactivity insertion) ==
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 +
<nowiki>
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set title "Time dependent simulation, zero reactivity insertion"
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 +
% --- Geometry is just a cube
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 +
surf 2 cuboid -100.0 100.0 -100.0 100.0 -100.0 100.0
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% --- Cell definitions:
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cell  3  0  fuel  -2
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cell 99  0  outside  2    % Outside world
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% --- Fuel material is a homogenized LWR material:
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 +
mat fuel  sum vol 8.0000E+06 moder lwtr 1001
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8016.03c  0.316667
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1001.03c  0.633333
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92235.03c 0.0015
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92238.03c 0.0485
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5010.03c  0.000115793 % 0$ reactivity insertion
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 +
% --- Thermal scattering data for hydrogen in light water (294 K)
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therm lwtr lwj3.00t
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 +
% --- Reflective boundary condition:
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set bc 2 2 2
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% --- Set up time structures for simulation and detectors:
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% --- 30 time bins for detector
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tme dettime 2 30 0 3e-3
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% --- 1 time interval for simulation (no population control)
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tme simutime 2 1 0 3e-3
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% --- Increase the size of neutron buffer since there is no pop. control
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set nbuf 10
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% --- Neutron population:
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% --- 300k neutrons in 300 batches (1000 neutrons per batch)
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set nps 60000000 6000 simutime
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% --- Link source
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set dynsrc "../crit/source" 1
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% --- Set up detectors:
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% --- Tally neutron population as a function of time
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det 1 dr -15 void di dettime
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% --- Tally fission energy deposition as a function of time
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det 2 dr -8 void di dettime
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% --- Save neutron and precursor source to "./source_end"-files
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set savesrc "./source_end"
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 +
% --- Do not generate group constants
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set gcu -1
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% --- Do not use implicit capture, nxn, or fission
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set impl 0 0 0
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</nowiki>
  
 
== Time dependent simulation (0.85$ reactivity insertion) ==
 
== Time dependent simulation (0.85$ reactivity insertion) ==

Revision as of 16:25, 15 March 2016

Generating the steady state source distributions

set title "Creating source for a time dependent simulation"

% --- Geometry is just a cube

surf 2 cuboid -100.0 100.0 -100.0 100.0 -100.0 100.0

% --- Cell definitions:

cell  3  0  fuel     -2
cell 99  0  outside   2     % Outside world

% --- Fuel material is a homogenized LWR material:

mat fuel   sum vol 8.0000E+06 moder lwtr 1001
 8016.03c  0.316667
 1001.03c  0.633333
 92235.03c 0.0015
 92238.03c 0.0485
 5010.03c  0.000115793

% --- Thermal scattering data for hydrogen in light water (294 K)

therm lwtr lwj3.00t

% --- Reflective boundary condition:

set bc 2 2 2

% --- Set power level

set power 1.0

% --- Neutron population:

% --- Large population size: (produced approx. 60M neutron and 40M precursor source points)
set pop 80000 80000 200 1.0 100

% --- Save neutron and precursor source to "./source"-files 

set savesrc "./source"

% --- Do not generate group constants

set gcu -1

% --- Do not use implicit capture, nxn, or fission

set impl 0 0 0

Time dependent simulation (no reactivity insertion)

set title "Time dependent simulation, zero reactivity insertion"

% --- Geometry is just a cube

surf 2 cuboid -100.0 100.0 -100.0 100.0 -100.0 100.0

% --- Cell definitions:

cell  3  0  fuel  -2
cell 99  0  outside   2     % Outside world

% --- Fuel material is a homogenized LWR material:

mat fuel   sum vol 8.0000E+06 moder lwtr 1001
 8016.03c  0.316667
 1001.03c  0.633333
 92235.03c 0.0015
 92238.03c 0.0485
 5010.03c  0.000115793 % 0$ reactivity insertion

% --- Thermal scattering data for hydrogen in light water (294 K)

therm lwtr lwj3.00t

% --- Reflective boundary condition:

set bc 2 2 2

% --- Set up time structures for simulation and detectors:

% --- 30 time bins for detector

tme dettime 2 30 0 3e-3

% --- 1 time interval for simulation (no population control)

tme simutime 2 1 0 3e-3

% --- Increase the size of neutron buffer since there is no pop. control

set nbuf 10

% --- Neutron population:

% --- 300k neutrons in 300 batches (1000 neutrons per batch)

set nps 60000000 6000 simutime

% --- Link source 

set dynsrc "../crit/source" 1

% --- Set up detectors:

% --- Tally neutron population as a function of time

det 1 dr -15 void di dettime

% --- Tally fission energy deposition as a function of time

det 2 dr -8 void di dettime

% --- Save neutron and precursor source to "./source_end"-files

set savesrc "./source_end"

% --- Do not generate group constants

set gcu -1

% --- Do not use implicit capture, nxn, or fission

set impl 0 0 0

Time dependent simulation (0.85$ reactivity insertion)