Why Does MCNP Delete Surfaces in Hexagonal Fuel Element Simulations?

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Discussion Overview

The discussion revolves around issues encountered while modeling a gas-cooled reactor with hexagonal fuel elements in MCNP, specifically focusing on the deletion of surfaces and resulting simulation errors. Participants explore the implications of surface deletion on the simulation's functionality and seek solutions to address particle loss and geometry errors.

Discussion Character

  • Technical explanation
  • Debate/contested
  • Mathematical reasoning

Main Points Raised

  • One participant notes that MCNP deletes coincident surfaces, which is a normal behavior, comparing it to overlapping objects on a surface.
  • Another participant expresses concern that the deletion of surfaces may lead to the loss of entire cells, resulting in particles being lost during the simulation.
  • It is suggested that lost particles typically indicate undefined volume within the simulation, pointing to potential issues beyond a specific cell that is not defined.
  • A later reply mentions that adding a void cell did not resolve the 'particle lost' and 'geometry error: no cell found' messages, indicating ongoing issues with cell definitions.
  • One participant inquires about the setup of the plotting package for MCNP, suggesting that dotted lines in the file may indicate improperly defined cells or overlaps.

Areas of Agreement / Disagreement

Participants express differing views on the causes of the simulation errors, with some attributing it to surface deletion and others to undefined volumes or overlaps in cell definitions. The discussion remains unresolved regarding the specific solutions to the errors encountered.

Contextual Notes

Limitations include potential missing assumptions about the geometry setup, dependence on the definitions of cells, and unresolved issues related to overlapping cells or undefined regions.

AlexFi
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TL;DR
tried to model gas cooled reactor, MCNP deleting surfaces
Hello
Tried to model gas cooled reactor with hexagonal fuel elements. MCNP keep deleting surfaces (If you could, run my input and check the .txto file) so the simulations won't run
Any advice?
 

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MCNP will delete coincident surfaces, this is normal. It's a bit like you have a table, and a chair, they might be complicated shapes but the bottom of all the legs of the table and the chair will be touching the floor, so you might have a lot of floor level surfaces that are actually all the same. When you build from macro bodies this will happen a lot, MCNP splits these into elementary surfaces and then gets rid of the duplicates.
 
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Thanks for the explanation. It seems to me that MCNP deleted the entire cell and the simulation won't run because particles got lost. What would be a solution for this?
 
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Usually particles getting lost means part of the volume is undefined. In this case there is something beyond cell 9, that isn't defined, and you have no void cell.
 
Made some minor changes, added void cell
Still getting 'particle lost' and 'geometry error:no cell found' error message
 

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Hi Alex,

Have you got the plotting package for MCNP set up? If you view your file you will see you have dotted lines. It means that MCNP thinks that some cells are not properly defined. They may be such that the cells overlap. Or that there are regions with no cell defined.
 

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