[MCNP5] Error when use Fm, De/Dm with Fmesh

[Khanh55]

Hello everyone,
I do need your help in this matter, please kindly help me solve this problem
I use MCNP5 and i run a simple example using Fmesh4 and Fm, De / Df but I get an error:
" fatal error. no tally associated with response function -1"
" fatal error. no tally associated with fm card -1 "

If I remove Fm and De / Df or replace Fmesh4 by F4 then there is no error.
Thank you!
input:

1 1 -1 3 5 -4 -2 -6 7
2 0 -1 #1
3 0 1

1 so 30
2 pz 0
3 pz -5
4 px 4
5 px -4
6 py 3
7 py -3

mode n
m1 1001.60c -0.111898 $Nuoc
8016.60c -0.888102
imp:n 1 1r 0 $ 1, 3
sdef pos= 0.00000000 0.00000000 15.00000000
vec= 0.00000000 0.00000000 -1.00000000
axs= 0.00000000 0.00000000 -1.00000000
ara= 78.53982
c The vecor defining the direction of each new particle is set to be
c perpedicular to the disk's surface
dir=1.0
c The angular sampling (mu) of the source is set to one, ensuring the
c particles are always traveling along the vec direction
c The dir and vec options ensure a monodirectional source
rad=d1
c The radial distribution from the axs vector is distribution d1 (si1,sp1)
erg=d2
c The energy distribution is described by si2,sp2
c
si1 0 5
c si1 specifies the radius is be between the discrete values of 0 and 5 cm
c sp1 -21 1
c sp1 specifies the distribtion is a power law p(x)=c|x|^a, where a=1
c This makes the source creation uniform over the disk's area
c si2 S 5 6 7
c Energy Distribution for "epithermal" neutron beam
c 10% thermal (<0.5 eV) 89% epithermal (0.5 eV to and 1% fast
c sp2 0.1 0.89 0.01
c sb2 0.05 0.15 0.8
# si2 sp2
0 0
1.00e-09 0.000609576
1.01e-07 0.99433306
2.01e-07 0.004941244
3.01e-07 8.46637E-05
4.01e-07 1.84198E-05
5.01e-07 8.43799E-06
6.01e-07 1.56881E-06
7.01e-07 1.02785E-06
8.01e-07 5.95067E-07
9.01e-07 9.73748E-07
1.00e-06 4.32776E-07
fmesh4:n origin -4 -0.5 -5 imesh 4 jmesh 0.5 kmesh 0&
iints 8 jints 1 kints 5 out=ik
fm4 1.11e9
# de4 df4
2.50e-08 3.67E-06
1.00e-07 3.67E-06
1.00e-06 4.46E-06
1.00e-05 4.54E-06
1.00e-04 4.18E-06
1.00e-03 3.76E-06
1.00e-02 3.56E-06
1.00e-01 2.17E-05
5.00e-01 9.26E-05
1 1.32E-04
2.5 1.25E-04
5 1.56E-04
7 1.47E-04
10 1.47E-04
14 2.08E-04
20 2.27E-04
nps 5e5

 

[Khanh55]

please, help me

 

[Astronuc]

I'm not a user of MCNP, however, I found the following example.

fm4 1.11e9

See some examples in https://dspace.mit.edu/bitstream/ha...51-fall-2005/contents/labs/lab4presentatn.pdf

Last page in linked file
c Reaction Rates
fc4 reaction rates
f4:n 1100
sd4 2.10829
e4 0.625E-6 20.0 T
fm4 (1.0 1000 (-6))
(1.0 1001 (102))

Earlier in the pdf
F4 Tally example

F4:N CELL#
FC4:N YOUR COMMENTS HERE
E4:N 0.5E-6 20 $ ENERGY STRUCTURE
FM4:N MULTIPLIERS

Make sure the syntax for FM, FM4 or F4 tally is correct for one's problem.

 

[Khanh55]

Thank you
But in this link do not use Fmesh, only use F4.
I'm sure my syntax is correct because in my article, if I replace Fmesh4 by F4 then run normally or use Fmesh4 and remove Fm, De / Df will run normally.
I have found an example in manual of MCNP5 that use Fmesh4 with Fm, De / Df (MCNP5_Lattice_Speed_Tally_Report__-_LAUR-04-3400. Page 35), but running on my laptop still have this error. I have tried running on some other laptop and still have the same error. Really can not understand

 

[PSRB191921]

Hi,
there are small problems in your file,
but if you revise the file it gives that :

The problem comes wth the SDEF definition you forgetted the "5 spaces" after:
vec, axs, ara, dir, rad, erg

I put my file which is ok with MCNP6 and Moritz,
hope it helps,
PSR

 

[Khanh55]

Hi,
there are small problems in your file,
but if you revise the file it gives that :

View attachment 209052

The problem comes wth the SDEF definition you forgetted the "5 spaces" after:
vec, axs, ara, dir, rad, erg

I put my file which is ok with MCNP6 and Moritz,
hope it helps,
PSR

Thank you very much.

I run your file with MCNP5 but still error, maybe MCNP5 can not use Fm, De / Df with Fmesh. Is there any way to be able to calculate Tally F4 the same as using Fmesh?
MCNP6 has been upgraded a lot, unfortunately my university does not have MCNP6, only MCNP5

 

[PSRB191921]

Hi,
I tried my file with MCNP5 and it's ok (see attached file) .
It's non ok with MCNPX.
When I look at your first post, it seams that you run MCNP with "vised". Probably "vised" runs MCNPX and not MCNP5. For that read your output file (ASCII file not with vised) and look the first lines: you can know what version of MCNP runs.
PSR

 

[Khanh55]

Hi,
Now I understand. MCNP5 v1.6 can do that.
How to get it ...? Real headache
thank you very much

 

[Khanh55]

Haha, success!
I copied the input file to the MCNP VisEd folder (bin folder), and run MCNP5 from CMD
Thanks everyone

 

[PSRB191921]

Cool for you
Hope I helped you a little bit
PSR