The structure input deck depends on the code one is using. Is one using TRACE?ayahsafety said:I am trying to make simulation of severe accidents in advanced nuclear reactors.
Can anybody advice me in how to write the input deck?
Is there any training materials about that?
Please, share your experience in simulationg nuclear reactors, problems you faced, etc.
Astronuc said:The structure input deck depends on the code one is using. Is one using TRACE?
To what kind of advanced reactor is one referring? Gen-III+ or Gen-IV?
There are training materials for most analytical codes. Usually a user's manual will have some example problems.
ayahsafety said:Actually, I will use TRACE and I'll try it to AP1000, Advanced Passive PWR.
Not many researchs were made using TRACE in AP1000, that's why I'm asking.
NUCENG said:Possible sources of information or advice:
http://www.lanl.gov/orgs/d/d5/teams/cfd.shtml
http://www.linkedin.com/in/yeonjongyoo
http://www.islinc.com/nuclear_systems_analysis.php
Even if they can't or won't help, they may have other contacts they can refer. Networking can be as good as a library. Try a web search for the TRACE Code and AP1000. Go to the NRC home page and try the same search. After all it is their go to code.
Good Luck.
The basic steps in modeling a nuclear reactor include defining the geometry and materials, specifying the nuclear and thermal properties, setting the boundary conditions, solving and analyzing the model, and validating the results.
The geometry and materials can be defined using computer-aided design (CAD) software or by creating a mesh for the reactor components. The materials must also be specified, including their composition, density, and other properties.
The important nuclear properties include the neutron flux, power distribution, and neutron multiplication factor. The thermal properties include heat transfer coefficients, temperature distribution, and thermal conductivity of the materials.
The boundary conditions include specifying the heat flux at the boundaries, as well as the neutron flux and power at the core boundary. Other considerations may include coolant flow rate and reactor power level.
The results of the model can be validated through comparison with experimental data or with results from other validated models. Sensitivity analysis can also be performed to ensure that the model is accurately capturing the behavior of the reactor.