MCNP4C: efficiency calculation

[lingleo]

Any one familiar with MCNP4C efficiency calculation can help me with this?
My cal. result for 1.836MeV(e.g.) is always small (6.16447E-05 ) compared to it should be(3.78E-004 by a professional business software), here is the inp file, is there anything wrong with the geometry define or source or tally card?
Thank you very much!
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---Cal of NaI sensitivity to be compared with Labsocs results
c cells
1 1 1.0 (1 -7 -12)#(1 -6 -11) imp:P=1
2 2 -7.86 (1 -6 -11)#(1 -5 -10) imp:P=1
3 3 -3.67 3 -4 -9 imp:P=1
4 4 -2.7 (2 -5 -10)#3 imp:P=1
5 5 -1.293e-3 -14 #1#2#3#4 imp:P=1
6 0 14 IMP:P=0

c surfaces(cm)
1 PY 0
2 PY 19.2
3 PY 19.56
4 PY 24.64
5 PY 25
6 PY 26
7 PY 41
9 CY 2.54
10 CY 2.9
11 CY 3.9
12 CY 20
14 SY 20.5 30

mode P
sdef cel=1 erg=D1 pos=0 0 0 axs=0 1 0 rad=D2 ext=D3 EFF=0.01
c for comparement
SI1 L 1.83608
c SI1 L 1.33249
c SI1 L 1.17322
c SI1 L 0.898
c SI1 L 0.66165
c SI1 L 0.514
SP1 D 1
SI2 0 20.6
SI3 -0.1 41.1
c M1 is H2O
M1 1001 0.6667 8016 0.3333 92235 0.966e-6
c M2 is Fe
M2 26056 1
c M3 is NaI
M3 11023 0.5 53127 0.5
c M4 is Al
M4 13027 1
c M5 is air
M5 8016 -0.231 7014 -0.7506 18040 -0.1286
F8:P 3
E8 0 1e-5 1 10I 1.8355 7I 1.8362
c E8 0 1e-5 1 10I 1.3321 7I 1.3328
c E8 0 1e-5 1 10I 1.1725 9I 1.1735
c E8 0 1e-5 0.1 10I 0.891 9I 0.901
c E8 0 1e-5 0.1 10I 0.510 9I 0.515
c E8 0 1e-5 0.1 10I 0.3910 9I 0.3920
c E8 0 1e-5 0.05 10I 0.3195 9I 0.3205
c E8 0 1e-5 0.05 10I 0.1582 9I 0.1592
c E8 0 1e-5 0.1 10I 0.6612 9I 0.6622
c E8 0 1e-5 0.01 13I 0.14 40I 0.145 0.15
c E8 0 1e-5 0.14366 11I 0.14378.
c E8 0 1e-5 0.05 0.1 10I 0.2045 9I 0.2055
c E8 0 1e-5 0.05 0.1 0.1850 9I 0.1860
c T6 0 10I 660e8
c fq6 t e
CTME 20
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[Norman]

This is a bad place to post this. I would suggest going to the MCNP forums:

http://www-xdiv.lanl.gov/x5/MCNP/forum.html

 

[sir-pinski]

I am not familiar with MCNP4C, but I can provide some general tips for troubleshooting efficiency calculations in MCNP.

First, make sure that your geometry is properly defined and all surfaces and cells are correctly specified. This includes checking for overlapping cells and making sure that all materials and densities are accurately defined.

Next, check your source definition to ensure that it is accurately representing the source you are trying to model. This includes the energy and location of the source.

You should also check your tally card to make sure that it is correctly tallying the quantity you are interested in.

If you have already checked these factors and are still getting incorrect results, it may be helpful to consult the MCNP user manual or reach out to other users on forums or discussion boards for further assistance.