2D PWR pin-cell burnup example

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% --- Pin-cell burnup calculation ----------------------------

set title "Pin-cell burnup calculation"

% --- Pin definition:

pin 1
fuel   0.412
clad   0.475
water

% --- Geometry:

surf 1  sqc 0.0 0.0 0.665

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

% --- Fuel (composition given in atomic densities):

mat fuel  -10.045  burn 1
92234.09c   6.15169E+18
92235.09c   6.89220E+20
92236.09c   3.16265E+18
92238.09c   2.17103E+22
 6012.09c   9.13357E+18
 7014.09c   1.04072E+19
 8016.09c   4.48178E+22

% --- Zircalloy cladding:

mat clad   -6.560
40000.06c  -0.9791
50000.06c  -0.0159
26000.06c  -0.0050

% --- Water (composition given in atomic densities):

mat water  -0.7569   moder lwtr 1001
 1001.06c   5.06153E+22
 8016.06c   2.53076E+22
 5010.06c   2.75612E+18
 5011.06c   1.11890E+19

% --- Thermal scattering data for light water:

therm lwtr lwj3.11t

% --- Cross section library file path:

set acelib "/xs/sss_endfb7u.xsdata"

% --- Periodic boundary condition:

set bc 3

% --- Neutron population and criticality cycles:

set pop 2000 500 20

% --- Geometry and mesh plots:

plot 3 500 500
mesh 3 500 500

% --- Decay and fission yield libraries:

set declib "/xs/sss_endfb7.dec"
set nfylib "/xs/sss_endfb7.nfy"

% --- Depletion steps:

% Power density 40 kW/kgU
% Depletion steps given in units of total burnup

set powdens 40.0E-3  

dep butot

0.1
0.5
1
2
3
4
5
6
7
8
9
10
12.5
15
17.5
20
25
30
35
40

% --- Isotope list for inventory calculation:

set inventory
922340
922350
922360
922380
932370
942380
942390
942400
942410
942420
952410
952430
420990
430990
441010
451030
471090
551330
621470
621490
621500
621510
621520
601430
601450
631530
641550

% ------------------------------------------------------------