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

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(Time dependent simulation (no reactivity insertion))
(Time dependent simulation (no reactivity insertion))
Line 99: Line 99:
 
% --- Neutron population:
 
% --- Neutron population:
  
% --- 300k neutrons in 300 batches (1000 neutrons per batch)
+
% --- 60M neutrons in 6k batches (1k neutrons per batch)
  
 
set nps 60000000 6000 simutime
 
set nps 60000000 6000 simutime

Revision as of 16:28, 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:

% --- 60M neutrons in 6k batches (1k neutrons per batch)

set nps 60000000 6000 simutime

% --- Link source (use point-wise precursor tracking)

set dynsrc "./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)

set title "Time dependent simulation, 0.85$ 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  0.000113    % 0.85$ 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:

% --- 60M neutrons in 6k batches (10k neutrons per batch)

set nps 60000000 6000 simutime

% --- Link source (use point-wise precursor tracking)

set dynsrc "./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