Recent content by HEU_LL
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MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly
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.- HEU_LL
- Post #3
- Forum: Nuclear Engineering
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MCNP6 BURN Card Issue: Zero Burnup for Material in Fuel Assembly
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...- HEU_LL
- Thread
- Burnup Mcnp6
- Replies: 2
- Forum: Nuclear Engineering
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Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)
Thank you very much for your enthusiasm and patient guidance. I deeply admire your excellent professional knowledge. With the two approaches you mentioned above, I have successfully resolved the issue. Once again, I sincerely appreciate your help. Wishing you all the best in your endeavors.- HEU_LL
- Post #7
- Forum: Nuclear Engineering
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Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)
Thank you very much for your patient guidance. Actually, I added Am241 and Am243 to the initial composition of the burnup materials and set them to a minute quantity of 1.0E-36, but the code failed to run and reported the following errors: “ fatal error. cross-section tables missing for zaid =...- HEU_LL
- Post #5
- Forum: Nuclear Engineering
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Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)
Thank you so much for your enthusiastic reply, which has been very encouraging. Based on your suggestions, I carefully studied the usage rules of the BURN card, but I did not find data for Am241 and Am243 in the output results. How should this issue be addressed?- HEU_LL
- Post #3
- Forum: Nuclear Engineering
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Beginner Seeking Help: MCNP6 Burnup Example (OECD-NEA Benchmark)
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...- HEU_LL
- Thread
- Burnup Mcnp6 phase i-b
- Replies: 6
- Forum: Nuclear Engineering