mcnp error

njm

Hi
I have problems in mcnp input of voxels. I define a voxel arrays and their universes,for example universe1 is defined as:
2001 43 -1.030 -70 u=1 vol=6.795352
but in runing I have below error:
fatal error.the surface type is not recognized: -1.03
While 1.03 is the density of material43!!!!

Can anyone help me?

QuantumPion

It sounds like you are trying to define a cell card in the surfaces section. Do you have an extra line break somewhere?

njm

oh yes!
thank you very much

njm

Now I have this error:
zero lattice element hit.
what is it?!
How can I solved it?!

Yrrepy

if you have a zero lattice element hit: it usually means you have a geometry error, overlapping cells, mis-defined cell surfaces etc

check out this primer

at the end is an excellent summary of common problems and their solutions

http://www.google.com/url?sa=t&rct=j...Ll32QV2VWK3LnQ

njm

Thanks you so much for your help.

flpojken

I am having the similar problems while running my script. I get this error

bad trouble in subroutine newcel of mcrun
source particle no. 2804404
starting random number = 132729341823053
zero lattice element hit.
run terminated because of bad trouble.

I suspect it has to do with something the code says before it starts that surface 42 appears more than once in a chain.
Does anyone have an idea of what it could be? And also the link to that primer doesn't work does anyone have a new link to it?

crnjak

Hi,
I am trying to do similar , but first I must learn basic stuff...
When I try to run code (down below) i get fatal error cell 2 have no fill???

1 1 -1 -1 fill=1 imp:n=1
2 1 -1 -2 lat=1 u=1 imp:n=1
3 0 1 imp:n=0

1 box -5 -5 -10 10 0 0 0 10 0 0 0 20
c 1 REC 0 0 0 0 0 70 20 0 0 0 10 0
2 box -5 -5 -10 1 0 0 0 1 0 0 0 1
c box -1 -1 -1 1 0 0 0 1 0 0 0 1

m1 94239.66c 1.0
c tally
f4:n 1 (2<2[0:9 0:9 0:19])
sdef pos .1 .1 .1
print

Any tips???

Cheers..