MCNP lattice of the fuel assembly input file?

[Islam Nabil]

TL;DR Summary

There is an input file of a simple lattice 16 x 16 fuel assembly. I have a message blocking the run of the code; bad trouble in subroutine newcel of mcrun source particle no 1 random number 6647299061401 zero lattice element hit. what is the wrong?

There is an input file for a simple 16 x 16 lattice fuel assembly. I have a message blocking the run of the code;
"bad trouble in subroutine newcel of mcrun source particle no 1 random number 6647299061401 zero lattice element hit."
What is wrong?

 

[Alex A]

There is an error somewhere in the geometry definition. If you change the filename of the input file to add .txt you can attach it to a post we can have a look at it.

If you can't share the input file you could try to debug it by plotting the geometry, but our help becomes very indirect.

 

[Islam Nabil]

There is an error somewhere in the geometry definition. If you change the filename of the input file to add .txt you can attach it to a post we can have a look at it.

If you can't share the input file you could try to debug it by plotting the geometry, but our help becomes very indirect.

Upload the txt file ...

 

[Alex A]

Yes, if you click the button 'Attach files' you can find the file, if the name ends .txt

 

[Islam Nabil]

Yes, if you click the button 'Attach files' you can find the file, if the name ends .txt

Already uploaded

 

[Islam Nabil]

Yes, if you click the button 'Attach files' you can find the file, if the name ends .txt

Name changed

 

[Alex A]

Sorry, maybe I needed to refresh the page or maybe I did not look at the first post!

Your lattice has universe 0 fills. I have not seen that before. You are cutting that out of the rpp being filled. Ok.

I did mcnp ip inp=file
Clicked to enter a command into the plot window and did,
pz 0
To see a cross section through the middle. Most fuel element positions are undefined. It will take me some time to look at this.

 

[Alex A]

Firstly your lattice is xz instead of xy.
fill=-8:9 -9:8 0:0
not
fill=-8:9 0:0 -9:8

Secondly the 0 universe fill is creating a space outside your (cooling?) tubes that is not defined. Changing the universe 0 entries to universe 1 fixes that. That is the usual way to create a 'background' cell, refer the lattice universe to itself. I don't see any other problems at the moment. The geometry errors seem to have gone and the input file now runs a kcode.

 

[Islam Nabil]

Firstly your lattice is xz instead of xy.
fill=-8:9 -9:8 0:0
not
fill=-8:9 0:0 -9:8

Secondly the 0 universe fill is creating a space outside your (cooling?) tubes that is not defined. Changing the universe 0 entries to universe 1 fixes that. That is the usual way to create a 'background' cell, refer the lattice universe to itself. I don't see any other problems at the moment. The geometry errors seem to have gone and the input file now runs a kcode.

Thank you, thank you very much, Doctor... The problem has already been resolved... Thank you...

 

[rpp]

I'm not sure what your final objectives are, but this assembly is at room temperature.
I've attached an input for a 16x16 case that uses a fuel temperature of 900 K and all other
temperatures are set at 600 K.

Unfortunately, this doesn't use lattices and the pin diameters are slightly different from what you have.

 

[Islam Nabil]

I'm not sure what your final objectives are, but this assembly is at room temperature.
I've attached an input for a 16x16 case that uses a fuel temperature of 900 K and all other
temperatures are set at 600 K.

Unfortunately, this doesn't use lattices and the pin diameters are slightly different from what you have.

Thanks a lot doctor... King regards