Abstract
In order to analyze the steady state and transient behavior of CNA‐II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA‐SA. Cross‐sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA‐II. The insertion of the rods is oblique, and a special routine was added to PARCS to treat this effect. CFD results combined with specialized mapping routines were used to model the boron injection system. In all cases there was good agreement in the results which provided confidence in the neutronics methods and modeling. A coupled code benchmark between U of M and U of Pisa is ongoing and results are still preliminary. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable.
Highlights
The objective of the work here was to develop and benchmark methods and models for the coupled neutronics and thermal-hydraulics analysis of the CNA-II reactor
All modeling was performed for the detailed design of the CNA-II reactor core and its particular control rod configuration and orientation
The NA-SA approach uses a rectangular representation of the core, and in order to compare with NA-SA, a PARCS model was developed that is very similar to this representation
Summary
Development for Coupled RELAP5/PARCS Analysis of the Atucha-II Nuclear Power Plant. In order to analyze the steady state and transient behavior of CNA-II, several tasks were required. Methods and models were developed in several areas. HELIOS lattice models were developed and benchmarked against WIMS/MCNP5 results generated by NA-SA. Cross-sections for the coupled RELAP5/PARCS calculation were extracted from HELIOS within the GenPMAXS framework. The validation of both HELIOS and PARCS was performed primarily by comparisons to WIMS/PUMA and MCNP for idealized models. Special methods were developed to model the control rods and boron injection systems of CNA-II. CFD results combined with specialized mapping routines were used to model the boron injection system. Under a LOCA transient, the best estimate behavior of the core appears to be acceptable
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