Difference between revisions of "FINIX PB2 example input"

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== Main Serpent input ==
 
== Main Serpent input ==
  
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<nowiki>
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% --- Asymmetric BWR assembly with Gd-pins -------------------
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set title "Peach Bottom 2 from UAM, FINIX calculation"
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include "/home/vvvillehe/Serpent2/serpdefaults.txt"
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include pins
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include geometry
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% --- Remember to set TMS limits for materials
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include materials_tft
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% --- Reflective boundary condition in XY, black in Z:
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set bc 2 2 1
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% --- Link FINIX input files
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set finrodfile      "./finixfiles/rod_library.txt"
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set finoptionsfile  "./finixfiles/options_library.txt"
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set finscenariofile "./finixfiles/scenario_library.txt"
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% --- Define sub-pin-level power binning
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% Name bin1, 6 radial zones in pellet, 24 axial zones
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finbin bin1 0.0 0.60579 6 -182.88 182.88 24
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% --- Link finix solvers for each pin type
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finrod 1 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
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finrod 2 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
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finrod 3 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
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finrod 4 rod_pb2_nogd  options_pb2_all scenario_pb2_all bin1
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finrod 5 rod_pb2_yesgd options_pb2_all scenario_pb2_all bin1
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% --- Neutron population and criticality cycles:
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% --- This is simulated on each iteration
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set pop 5000 10 100
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% --- This is the number of iterations
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set ccmaxiter 10
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% --- Use a smaller number of inactive cycles after each FINIX solution
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% --- (Fission source passing on, number of alternative cycles is 10)
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set fsp 1 10
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% --- Total power
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set power 3.9429e+06
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% --- Geometry and mesh plots:
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plot 3 1000 1000 0.0
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plot 3 1000 1000 0.0 -22.86 7.62 -22.86 7.62
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plot 2 500 1500
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plot 1 500 1500
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% --- xy-plot of fission power / thermal flux
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mesh 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0
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% --- xz-plot of fission power / thermal flux
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mesh 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0
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% --- xy-plot of temperature distribution / thermal flux
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mesh 10 3 1000 1000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0
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% --- xz-plot of temperature distribution / thermal flux
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mesh 10 2 1000 3000 0 -7.62 7.62 -7.62 7.62 -250.0 250.0
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</nowiki>
  
 
== References ==
 
== References ==
 
<references/>
 
<references/>

Revision as of 14:17, 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"
include "/home/vvvillehe/Serpent2/serpdefaults.txt"
include pins

include geometry

% --- Remember to set TMS limits for materials

include materials_tft

% --- 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

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
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