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

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The discussion revolves around a burnup calculation issue in MCNP6, where one material in a fuel assembly shows zero burnup information despite being defined similarly to another material that burns up normally. The user is seeking insights into why Material 2 is not processing burnup data correctly, while Material 1 functions as expected. Suggestions include verifying that both materials are correctly listed on the MAT card and sharing a simplified version of the problem if the original cannot be disclosed. The conversation emphasizes troubleshooting and collaboration to resolve the issue effectively. The user is looking for practical advice to address the burnup calculation discrepancy.
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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!
 
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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?
 
Alex A said:
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.
 
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...
Hi everyone, I'm a complete beginner with MCNP and trying to learn how to perform burnup calculations. Right now, I'm feeling a bit lost and not sure where to start. I found the OECD-NEA Burnup Credit Calculational Criticality Benchmark (Phase I-B) and was wondering if anyone has worked through this specific benchmark using MCNP6? If so, would you be willing to share your MCNP input file for it? Seeing an actual working example would be incredibly helpful for my learning. I'd be really...
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