Basic steps in modeling a nuclear reactor

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SUMMARY

This discussion focuses on modeling severe accidents in advanced nuclear reactors, specifically using the TRACE code for the AP1000, an Advanced Passive Pressurized Water Reactor (PWR). Participants emphasize the importance of the input deck structure, which varies depending on the analytical code used. They recommend consulting user manuals and training materials, which typically include example problems. Networking and web searches for resources related to TRACE and AP1000 are also suggested as effective strategies for gathering information.

PREREQUISITES
  • Understanding of TRACE code for thermal-hydraulic analysis
  • Familiarity with advanced reactor types, specifically Gen-III+ and Gen-IV
  • Knowledge of input deck structure for simulation codes
  • Access to user manuals and training materials for analytical codes
NEXT STEPS
  • Research TRACE code documentation and user manuals for AP1000 simulations
  • Explore training materials specific to advanced nuclear reactor modeling
  • Investigate networking opportunities with professionals in nuclear systems analysis
  • Conduct web searches for case studies on TRACE applications in AP1000 scenarios
USEFUL FOR

Nuclear engineers, researchers in reactor safety analysis, and professionals involved in advanced nuclear reactor simulations will benefit from this discussion.

ayahsafety
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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.
 
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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.
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.
 
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.

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.
 
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.

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.
 
Last edited by a moderator:
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.

Thank you very much. I will try with these pages.

Best regards.
 
Last edited by a moderator:

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