mcnp error


by njm
Tags: error, mcnp
njm
njm is offline
#1
Feb22-12, 07:30 AM
P: 7
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?
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QuantumPion
QuantumPion is offline
#2
Feb22-12, 10:04 AM
P: 731
Quote Quote by njm View Post
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?
It sounds like you are trying to define a cell card in the surfaces section. Do you have an extra line break somewhere?
njm
njm is offline
#3
Feb24-12, 11:37 PM
P: 7
oh yes!
thank you very much

njm
njm is offline
#4
Feb24-12, 11:40 PM
P: 7

mcnp error


Now I have this error:
zero lattice element hit.
what is it?!
How can I solved it?!
Yrrepy
Yrrepy is offline
#5
Feb27-12, 07:35 AM
P: 14
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
njm is offline
#6
Feb27-12, 11:15 PM
P: 7
Thanks you so much for your help.
flpojken
flpojken is offline
#7
Jan7-13, 04:38 AM
P: 8
Quote Quote by Yrrepy View Post
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
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
crnjak is offline
#8
May14-13, 06:56 AM
P: 5
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..


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