Where Can I Find Resources and Tips for Coding PARET?

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SUMMARY

The discussion focuses on resources and tips for coding PARET, a tool primarily applicable to small research and test reactors. Key resources include the "THERMAL-HYDRAULIC ASPECTS OF FLOW INVERSION IN A RESEARCH REACTOR" paper and the "MNSR Transient Analyses and Thermal-Hydraulic Safety Margins for HEU and LEU Cores Using PARET" study. Additional references include the PARET-ANL code system available through OECD-NEA and guidance from users at Argonne National Laboratory (ANL). These resources provide essential insights into the thermal-hydraulic analysis of reactor cores.

PREREQUISITES
  • Understanding of thermal-hydraulic principles in reactor design
  • Familiarity with PARET code functionalities and applications
  • Knowledge of research reactor operations and safety margins
  • Basic skills in analyzing transient behaviors in reactor cores
NEXT STEPS
  • Explore the "THERMAL-HYDRAULIC ASPECTS OF FLOW INVERSION IN A RESEARCH REACTOR" paper for foundational concepts
  • Review the "MNSR Transient Analyses and Thermal-Hydraulic Safety Margins for HEU and LEU Cores Using PARET" study for practical applications
  • Investigate the PARET-ANL code system documentation available from OECD-NEA
  • Contact Argonne National Laboratory for expert guidance on PARET usage
USEFUL FOR

This discussion is beneficial for researchers, engineers, and safety analysts involved in the design and analysis of research reactors, particularly those utilizing the PARET code for thermal-hydraulic assessments.

khalid03ma
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Please let me know if there is any resources, papers or tips and tricks to code PARET
 
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khalid03ma said:
Please let me know if there is any resources, papers or tips and tricks to code PARET

PARET seems to have limited application to small research and test reactors, most of which it seems are cooled by natural convection.

THERMAL-HYDRAULIC ASPECTS OF FLOW INVERSION IN A RESEARCH REACTOR
http://www.iaea.org/inis/collection/NCLCollectionStore/_Public/18/066/18066087.pdf


MNSR Transient Analyses and Thermal-Hydraulic Safety Margins for HEU and LEU Cores Using PARET
http://www.rertr.anl.gov/RERTR29/Abstracts/S16-2_Olson.html

https://rsicc.ornl.gov/codes/psr/psr5/psr-565.html
PARET-ANL(NESC): Code System to Predict Consequences of Nondestructive Accidents in Research and Test Reactor Cores

The code seems to be available from OECD-NEA
http://www.oecd-nea.org/tools/abstract/detail/psr-0516

If one wishes some guidance, then perhaps one should contact those who use the code at ANL.


Using PARET Code for Analyzing Research Reactor Cores with Two Fuel Geometries
http://www.rertr.anl.gov/RERTR34/pdfs/S8-P1_Badry.pdf
 
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