PTRAC File - MCNP - Multi-core computing

AI Thread Summary
Luiz, a postdoc in Brazil, is seeking guidance on generating a PTRAC file for a cold neutron source using MCNP 6.2, specifically through multi-core computing. The discussion highlights the importance of PTRAC files in modeling and raises questions about the limitations of thermal scattering libraries at low temperatures. Concerns about CPU capacity and the feasibility of streaming large event data to disk are also addressed. Participants inquire about the specifics of the computing setup, including whether to use OpenMP or MPI for execution. The conversation emphasizes the technical requirements and potential challenges in obtaining the PTRAC file.
Luizpo
Messages
1
Reaction score
0
Homework Statement:: PTRAC File - MCNP - Multi-core computing
Relevant Equations:: No equations

My name is Luiz. I am a postdoc at the institute of energy and nuclear research in São Paulo-Brazil.
Our group models a cold neutron source (CNS) for the Brazilian multipurpose reactor project, through MCNP 6.2.
We need a PTRAC file in the CNS region and would like to know if it is possible to obtain this file through multi-core computing. If yes, how should we execute it?
 
Engineering news on Phys.org
I may not be the right person to answer, but this sounds interesting. I assume you will be basing this off the libraries .05c or 0.85c, but the thermal scattering libraries have very few options at low temperature. Is your setup 18 liters of liquid deuterium at 20K?

Why is PTRAC important and will it have very narrow criteria? Only I'm not sure CPU capacity will be limiting if it's streaming a large number of events to disk. What do you know of the computer, do you need to use OpenMP or MPI?
 
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...
Back
Top