MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly

[HEU_LL]

TL;DR

I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information for Material 2 is zero, while Material 1 appears to be burning up normally.

Hello everyone,

I am currently working on a burnup calculation for a fuel assembly with repeated geometric structures using MCNP6. I have defined two materials (Material 1 and Material 2) which are actually the same material but located in different positions. However, after running the calculation with the BURN card, I am encountering an issue where all burnup information（power fraction(Initial input is 1,but output file is 0), burnup, mass, etc.） for Material 2 is zero, while Material 1 appears to be burning up normally.
Has anyone encountered a similar issue or have insights into what might be causing this problem? Any suggestions or advice would be greatly appreciated. Thank you in advance for your help!

 

[Alex A]

I'm assuming since you get answers both materials are on your MAT card. Can you show us what isn't working by renaming it to a .txt and attaching it to a post please?

If you are not allowed to share it can you cut down the problem to something simple that has the same behavior and share that please?

 

[HEU_LL]

I'm assuming since you get answers both materials are on your MAT card. Can you show us what isn't working by renaming it to a .txt and attaching it to a post please?

If you are not allowed to share it can you cut down the problem to something simple that has the same behavior and share that please?

I'm very sorry to disturb everyone. The problem has been solved. In fact, it was due to carelessness that I wrote the wrong number of the materials that needed to be burned. I'm new to this forum and still don't know how to delete this help-seeking post.