Difference between revisions of "FINIX PB2 example input"

Revision as of 15:23, 1 December 2015

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.

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

% --- 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"

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

finbin bin1 0.0 0.60579 6 -182.88 182.88 24

% --- 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 10 100

% --- This is the number of iterations

set ccmaxiter 10

% --- Use a smaller number of inactive cycles after each FINIX solution
% --- (Fission source passing on, number of alternative cycles is 10)

set fsp 1 10

% --- Total power

set power 3.9429e+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

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 

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