FINIX PB2 CE example input

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Revision as of 16:13, 4 January 2017 by Ville Valtavirta (Talk | contribs) (Main Serpent input)

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Note: FINIX currently does not include models for many burnup related changes in the fuel rods. The fuel behavior solution will be for fresh fuel at all burnups.

Example of coupled burnup calculations using FINIX. The depletion scheme used is explicit Euler's method with stochastic approximation based relaxation applied to the transmutation cross sections and one-group fluxes used for the depletion solution.

The input model is based on the Peach Bottom 2 BWR assembly from the UAM benchmark [1] with the segmented absorber rod replaced by a full length one. For simplicity the Serpent input has been divided into multiple files using the include card.

Main Serpent input

% --- Asymmetric BWR assembly with Gd-pins -------------------

set title "Peach Bottom 2 from UAM, FINIX calculation"

% --- Remember to set TMS limits for materials

include materials

include pins

include geometry

include volumes

% --- Reflective boundary condition in XY, black in Z:

set bc 2 2 1

% --- Link FINIX input files

set finrodfile      "./finixfiles/rod_library.txt"
set finoptionsfile  "./finixfiles/options_library.txt"
set finscenariofile "./finixfiles/scenario_library.txt"

include "/home/vvvillehe/Serpent2/serpdefaults.txt"

% --- Define sub-pin-level power binning for FINIX
% Name bin1, 6 radial zones in pellet, 24 axial zones

finbin bin1 0.0 0.60579 6 -182.88 182.88 10

% --- Link finix solvers for each pin type

finrod 1 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
finrod 2 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
finrod 3 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
finrod 4 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
finrod 5 rod_pb2_yesgd options_pb2_all scenario_pb2_all bin1

% --- Neutron population and criticality cycles:
% --- This is simulated on each iteration

set pop 5000 50 100

% --- This is the number of iterations for each neutronics solution

set ccmaxiter 2

% --- Use a smaller number of inactive cycles on subsequent neutron transport solutions
% --- (Fission source passing on, number of alternative cycles is 50)

set fsp 1 50

% --- Depletion scheme (constant extrapolation, i.e., Explicit euler)

set pcc ce

% --- Depletion history (just two steps)

dep daystep 5 5

% --- Use a lower optimization mode to save memory

set opti 1

% --- Division of materials to depletion zones

div fuel1 sep 0 subz 10 -182.88 182.88 
div fuel2 sep 0 subz 10 -182.88 182.88 
div fuel3 sep 0 subz 10 -182.88 182.88 
div fuel4 sep 0 subz 10 -182.88 182.88 
div fuel5 sep 0 subz 10 -182.88 182.88 subr 5 0.0 0.60579

% --- Total power

set power 3.0e+06

% --- Geometry and mesh plots:

plot 3 1000 1000 0.0 
plot 3 1000 1000 0.0 -22.86 7.62 -22.86 7.62
plot 2 500 1500
plot 1 500 1500

% --- xy-plot of fission power / thermal flux

mesh 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0

% --- xz-plot of fission power / thermal flux

mesh 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0

% --- xy-plot of temperature distribution / thermal flux

mesh 10 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0

% --- xz-plot of temperature distribution / thermal flux

mesh 10 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0

Additional Serpent files

materials file

% --- Fuel materials, TMS limits 557 K and 2100 K:

% Fuel1 2.93 wt % enrichment
mat fuel1   -10.42 tft 557.0 2100.0 rgb 100 0 0
92235.03c   -0.0258279
92238.03c   -0.85567041
8016.03c    -0.11850169

% Fuel2 1.94 wt % enrichment
mat fuel2   -10.42 tft 557.0 2100.0 rgb 160 0 0
92235.03c   -0.01710132
92238.03c   -0.86441006
8016.03c    -0.11848862

% Fuel3 1.69 wt % enrichment
mat fuel3   -10.42 tft 557.0 2100.0 rgb 200 75 75
92235.03c   -0.0148976
92238.03c   -0.86661708
8016.03c    -0.11848532

% Fuel4 1.33 wt % enrichment
mat fuel4   -10.42 tft 557.0 2100.0 rgb 255 150 150
92235.03c   -0.01172421
92238.03c   -0.86979522
8016.03c    -0.11848057

% --- Fuel with Gd, TMS limits 557 K and 2100 K:

% Fuel5 2.93 wt % enrichment, 3.0 wt% Gadcontent
mat fuel5   -10.25 tft 557.0 2100.0 rgb 0 100 0
92235.03c   -0.02505306
92238.03c   -0.8300003
8016.03c    -0.11891791
64152.03c   -0.00005029
64154.03c   -0.00055541
64155.03c   -0.00379519
64156.03c   -0.00528302
64157.03c   -0.004065
64158.03c   -0.00649317
64160.03c   -0.00578667

% --- Zirc2 cladding, TMS limits 557 K and 1000 K:

mat Zirc2 -6.56000E+00 tft 557.0 1000.0 rgb 200 200 200
 8016.03c  -1.19376E-03
24052.03c  -8.34483E-04
26056.03c  -9.16258E-04
28058.03c  -3.35317E-04
28060.03c  -1.33612E-04
28062.03c  -1.91358E-05
40090.03c  -4.98111E-01
40091.03c  -1.09835E-01
40092.03c  -1.69731E-01
40094.03c  -1.75753E-01
40096.03c  -2.89183E-02
50112.03c  -1.27668E-04
50116.03c  -1.98205E-03
50117.03c  -1.05596E-03
50118.03c  -3.35857E-03
50119.03c  -1.20129E-03
50120.03c  -4.59450E-03
50122.03c  -6.63830E-04
50124.03c  -8.43778E-04

% --- Assembly box treated as zircaloy, composition is the same as
%     Zirc2, but has to be separate as the temperature is constant

mat box      -6.56000E+00 tmp 557.0 rgb 200 200 200
 8016.03c  -1.19376E-03
24052.03c  -8.34483E-04
26056.03c  -9.16258E-04
28058.03c  -3.35317E-04
28060.03c  -1.33612E-04
40090.03c  -4.98111E-01
40091.03c  -1.09835E-01
40092.03c  -1.69731E-01
40094.03c  -1.75753E-01
40096.03c  -2.89183E-02
50112.03c  -1.27668E-04
50116.03c  -1.98205E-03
50117.03c  -1.05596E-03
50118.03c  -3.35857E-03
50119.03c  -1.20129E-03
50120.03c  -4.59450E-03
50122.03c  -6.63830E-04
50124.03c  -8.43778E-04

% --- "Steel, Stainless 304" [PNNL-15870, Rev. 1]

mat ssteel -8.00000E+00 tmp 557.0 rgb 100 100 100
 6012.03c  -3.95366E-04
14028.03c  -4.59332E-03
14029.03c  -2.41681E-04
14030.03c  -1.64994E-04
15031.03c  -2.30000E-04
16032.03c  -1.42073E-04
24050.03c  -7.93000E-03
24052.03c  -1.59029E-01
24053.03c  -1.83798E-02
24054.03c  -4.66139E-03
25055.03c  -1.00000E-02
26054.03c  -3.96166E-02
26056.03c  -6.44901E-01
26057.03c  -1.51600E-02
26058.03c  -2.05287E-03
28058.03c  -6.21579E-02
28060.03c  -2.47678E-02
28061.03c  -1.09461E-03
28062.03c  -3.54721E-03
28064.03c  -9.32539E-04

% --- Coolant (40% void fraction):

mat cool     -0.46072  moder lwtr 1001 tmp 557 rgb 150 150 255
 1001.03c     0.66667
 8016.03c     0.33333

% --- Moderator:

mat moder    -0.46072  moder lwtr 1001 tmp 557 rgb 50 50 255
 1001.03c     0.666667
 8016.03c     0.333333

% --- Thermal scattering data for light water:

% (HinH20 at 573.60K)
therm lwtr lwj3.11t 

pins file

% --- Empty lattice position:

pin 99
cool   

% --- Fuel pins:

pin 1
fuel1  0.60579
void   0.62103
Zirc2  0.71501
cool

pin 2
fuel2  0.60579
void   0.62103
Zirc2  0.71501
cool

pin 3
fuel3  0.60579
void   0.62103
Zirc2  0.71501
cool

pin 4
fuel4  0.60579
void   0.62103
Zirc2  0.71501
cool

pin 5
fuel5  0.60579
void   0.62103
Zirc2  0.71501
cool

geometry file

lat 100 1  0.23876  0.23876 9 9 1.875 % *
99 99 99 99 99 99 99 99 99
99  4  3  3  2  2  2  3 99
99  3  2  1  1  1  1  2 99
99  3  1  5  1  1  5  1 99
99  2  1  1  1  1  1  2 99
99  2  1  1  1  5  1  1 99
99  2  1  5  1  1  1  2 99
99  3  2  1  1  1  2  2 99
99 99 99 99 99 99 99 99 99 


% --- Outer channel (assembly pitch = 15.375):

surf  1  sqc   0.23876  0.23876  6.70306 % *
surf  2  sqc   0.23876  0.23876  6.90626

% --- Axial limits of the active part

surf  4  pz -182.88 % Active stack length 365.76 cm
surf  5  pz  182.88 % Active stack length 365.76 cm

% --- Boundary of one assembly cell

surf  9  cuboid  -7.62 7.62 -7.62 7.62 -250.0 250.0

% --- Cell definitions:

cell  3  101  fill 100  -1          % Pin lattice
cell  4  101  box        1          % Channel box wall

cell  5  0  fill 101   -2 4 -5      % assembly inside channel box outer wall
cell  6  0  moder       2 4 -5 -9   % Water outside channel box
cell  9  0  moder        -4    -9   % bottom reflector
cell 10  0  moder            5 -9   % top reflector

cell 99  0  outside             9   % Outside world

FINIX input files

rod_library.txt file

! Peach Bottom 2 BWR rod from UAM description
! No gadolinia

begin rod_pb2_nogd

pellet_inner_radius = 0.0             
pellet_outer_radius = 6.0579e-03      
clad_inner_radius = 6.2103e-03    
clad_outer_radius = 7.1501e-03    
fuel_axial_length = 3.6576
clad_axial_length = 3.6576

plenum_length = 0.4013               

pellet_roughness = 2.0e-6
fractional_density = 0.951
gadolinia_weight_fraction = 0.0

clad_roughness = 0.5e-6
coldwork = 0.5                
clad_oxygen_concentration = 0.0012      
fast_neutron_fluence = 0.0    

! Fill gas pressure (Pa)
fill_gas_pressure = 0.69e6

! As-fabricated fill-gas temperature
fill_gas_temperature = 300.0

! Fill gas fractions
gas_fraction_He = 1.0
gas_fraction_Ar = 0.0
gas_fraction_Kr = 0.0
gas_fraction_Xe = 0.0
gas_fraction_H2 = 0.0
gas_fraction_N2 = 0.0
gas_fraction_H2O = 0.0

! Rod pitch
pitch = 18.75e-3

! Number of rods in unit cell (1.0 in square, 0.5 in triangular lattice)
unitcell = 1.0

end rod_pb2_nogd


! Peach Bottom 2 BWR rod from UAM description
! 3.0 wt-% gadolinia

begin rod_pb2_yesgd

pellet_inner_radius = 0.0             
pellet_outer_radius = 6.0579e-03      
clad_inner_radius = 6.2103e-03    
clad_outer_radius = 7.1501e-03    
fuel_axial_length = 3.6576
clad_axial_length = 3.6576

plenum_length = 0.4013               

pellet_roughness = 2.0e-6
fractional_density = 0.951
gadolinia_weight_fraction = 0.03

clad_roughness = 0.5e-6
coldwork = 0.5                
clad_oxygen_concentration = 0.0012      
fast_neutron_fluence = 0.0    

! Fill gas pressure (Pa)
fill_gas_pressure = 0.69e6

! As-fabricated fill-gas temperature
fill_gas_temperature = 300.0

! Fill gas fractions
gas_fraction_He = 1.0
gas_fraction_Ar = 0.0
gas_fraction_Kr = 0.0
gas_fraction_Xe = 0.0
gas_fraction_H2 = 0.0
gas_fraction_N2 = 0.0
gas_fraction_H2O = 0.0

! Rod pitch
pitch = 18.75e-3

! Number of rods in unit cell (1.0 in square, 0.5 in triangular lattice)
unitcell = 1.0

end rod_pb2_yesgd

options_library.txt file

! Basic options for the Peach Bottom 2 simulation

begin options_pb2_all

! Number of nodes in the thermal/mechanical solution

axial_nodes = 24
pellet_radial_nodes = 51
clad_radial_nodes = 21

! Boundary condition is fixed cladding outer temperature
! NB: This must be given in the scenario

boundary_option = 0

end options_pb2_all

scenario_library.txt file

! Basic scenario for Peach Bottom 2 simulations using clad surface temperature
! as a boundary condition

begin scenario_pb2_all

! Clad temperature history 

! Only one axial zone 
clad_temperature_history_zones = 3.6576

! Temperature, time pairs for first axial zone
! Only one time point now
clad_temperature_history(1) = 570.0, 0.0

end scenario_pb2_all

References

  1. ^ Ivanov et al. "Benchmarks for Uncertainty Analysis in Modelling (UAM) for the Design, Operation and Safety Analysis of LWRs, Volume I: Specification and Support Data for Neutronics Cases (Phase I), Version 2.1", NEA/NSC/DOC(2013)7