Fuel Assembly in Water Tank
c ********************************* cells *******************************
11 313 -10.44   -71     u=1 imp:n=1 $ Fuel
12 201  -6.55   -72 71  u=1 imp:n=1 $ Cladding
13 101  -1.00       72  u=1 imp:n=1 $ Outside u=1 world
21 101  -1.00      -73  u=5 lat=1        imp:n=1 $ Infinite lattice
         fill=-6:6 -6:6 0:0 
         5 1 1 1 1 1 1 1 1 8 8 8 8
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
         1 1 1 1 1 1 1 1 1 1 1 1 1
31 0            -74      fill=5 imp:n=1 $ Assembly containing cell
32 101  -1.00    74 -75         imp:n=1 $ Water tank
99 0                 75         imp:n=0 $ Outside world
16 102  -10.5   -76         u=8 imp:n=1 $ Depleted uranium pin 
17 101  -1.00        76     u=8 imp:n=1 $ Outside u=8 world         

c ****************************** surfaces *******************************
71 RCC 0 0 -150   0 0 300  .4840        $ fuel cylinder
72 RCC 0 0 -150   0 0 300  .5590        $ clad cylinder
73 RPP -.75 .75  -.75 .75  -150 150     $ Fuel assembly box
74 RPP -9.75 9.75  -9.75 9.75  -150 150 $ Fuel assembly boundary
75 RCC 0 0 -200   0 0 400   30          $ water tank
76 RCC 0 0 -150   0 0 300  .7000        $ depleted uranium tube

c ********************************* data ********************************
SDEF PAR=SF  pos=0 0 0  ext=d61  axs=0 0 1  rad=fcel=d50   cel=d63
si61 -150 150
sp61    0   1
si63 L   (11<21[-5:2  -6:-6 0:0]<31)
         (16<21[ 3:6  -6:-6 0:0]<31)
         (11<21[-6:6  -5:6  0:0]<31)
sp63      2.68 7R  5.80 3R  2.68 155R
DS50 S      51 7R    52 3R    51 155R
si51    0 .4840
sp51 -21 1
si52    0 .700
sp52 -21 1
print
nps 1e4
prdmp 2J 1
m102   92235.80c .003  92238.80c .997  8016.80c 2 $ depleted uranium
m201   40090 -0.505239   40091 -0.110180   40092 -0.168413
       40094 -0.170672   40096 -0.027496   nlib=80c      $ zirconium
m313   92235.80c -0.02759 92238.80c -0.85391 8016.80c -0.1185  $ UO2
m101   1001.80c 2 8016.80c 1                                 $ water
mt101 lwtr
c
FC4 Induced fission neutrons in enriched and depleted fuel pins
F4:n    (11<(21[-5:2  -6:-6 0:0])<31) (11<(21[-6:6  -5:6  0:0])<31)
        (16<(21[ 3:6  -6:-6 0:0])<31)
FQ4 F M
FM4 (-1 102 -6 -7) (-1 313 -6 -7)
sd4 1 2R
