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