HTGR particle-cell burnup example

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set title "HTGR Depletion Benchmark, Infinite Lattice Grain Model"  

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% Geometry:

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% --- Coated particle:

particle 1

fuel    0.0250
buffer  0.0340
PyC     0.0380
SiC     0.0415
PyC     0.0455
matrix

% --- Lattice cell

surf 1 cube 0.0 0.0 0.0 0.081705

cell 1 0 fill 1  -1
cell 2 0 outside  1

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% Material data:

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% -- Fuel:

mat fuel   -10.4          burn 1

92238.03c    2.12877E-02
92235.03c    1.92585E-03
 8016.03c    4.64272E-02
 5010.03c    1.14694E-07
 5011.03c    4.64570E-07

% --- Carbon buffer layer:

mat buffer  -1.05         moder grph 6000

 6000.03c    5.26449E-02

% --- Pyrolytic carbon layer:

mat PyC     -1.90         moder grph 6000

 6000.03c    9.52621E-02

% --- Silicon carbide layer:

mat SiC     -3.18

14000.03c    4.77240E-02
 6000.03c    4.77240E-02

% --- Graphite matrix:

mat matrix  -1.75         moder grph 6000  burn 1 vol 0.0039689

 6000.03c    8.77414E-02
 5010.03c    9.64977E-09
 5011.03c    3.90864E-08

% --- Thermal scattering data:

therm grph gre7.00t

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% Calculation parameters:

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% --- Geometry plot:

plot 3 500 500

% --- Libraries:

set acelib "/xs/sss_endfb7u.xsdata"
set declib "/xs/sss_endfb7.dec"
set nfylib "/xs/sss_endfb7.nfy"

% --- Energy grid:

set egrid 2E-6 1E-10 15.0
set dix 1

% --- Boundary conditions:

set bc 3

% --- Histories:

set pop 2000 500 10

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% Detectors:

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% --- Detector materials:

mat m92238  1.0 92238.03c 1.0
mat m92235  1.0 92235.03c 1.0

% --- Energy grid structures:

ene 1 1 1E-11 0.625E-6 20.0
ene 2 3 1000 1E-11 20.0

% --- Spectral indices (in fuel):

det 1 de 1 dm fuelp1r1 dr 102 m92238
det 2 de 1 dm fuelp1r1 dr  18 m92235
det 3      dm fuelp1r1 dr  18 m92235 dr  18 m92238
det 4      dm fuelp1r1 dr  18 m92235 dr 102 m92238

% --- Spectrum:

det 10 de 2

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% Burnup calculation:

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% --- Options:

set fpcut 1E-6
set stabcut 0.0
set xsfcut  0.0
set pcc 1

% --- Power density

set powdens 62.0E-3

% --- Irradiation history:

dep butot

   0.1
   0.5
   1.0
   2.0
   3.0
   4.0
   5.0
   6.0
   7.0
   8.0
   9.0
  10.0
  12.0
  14.0
  16.0
  18.0
  20.0
  22.0
  24.0
  26.0
  28.0
  30.0
  32.0
  34.0
  36.0
  38.0
  40.0
  45.0
  50.0
  55.0
  60.0
  65.0
  70.0
  75.0
  80.0
  85.0
  90.0
  95.0
 100.0
 105.0
 110.0
 115.0
 120.0

% --- Nuclide inventory:

set inventory

% Actinides: 

922350
922380
942390
942400
942410
942420
952410
952440
952450

% Fission products:

360850
380900
471101
551370
541350
621490
621510

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