Infinite homogeneous LWR-like reactor transient example

Note: For transient simulations, the initial system needs to be as close to criticality as possible. The exact multiplication factor of the system may vary if different cross section libraries is used. In that case, adjust the boron content in the fuel material to achieve criticality.

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 (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

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