Title of article
On the use of RELAP5-3D as a subchannel analysis code Original Research Article
Author/Authors
Matthew Memmott، نويسنده , , Jacopo Buongiorno، نويسنده , , Pavel Hejzlar، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2010
Pages
9
From page
807
To page
815
Abstract
The capabilities of the RELAP5-3D code to perform subchannel analyses in sodium-cooled fuel assemblies were evaluated. The motivation was the desire to analyze fuel assemblies with traditional (solid pins) as well as non-traditional (e.g., annular pins with internal cooling, bottle-shape) geometries. Since no current subchannel codes can handle such fuel assembly designs, a new flexible RELAP5-based subchannel model was developed. It was shown that subchannel analysis of sodium-cooled fuel assemblies is indeed possible through the use of control variables in RELAP5. The subchannel model performance was then verified and validated in code-to-code and code-to-experiment analyses, respectively. First, the model was compared to the SUPERENERGY II code for solid fuel pins in a conventional hexagonal lattice. It was shown that the temperature predictions from the two codes agreed within 2% (<3.5 °C). Second, the model was applied to the Oak Ridge 19-pin test, and it was found that the measured outlet temperature distribution could be predicted with a maximum error of 8% (<7 °C). Furthermore, the use of semicircular ribs on the duct wall to flatten the temperature distribution in a traditional hexagonal assembly was explored by means of the newly developed RELAP5-3D subchannel model; the results are reported here as an example of the model capabilities.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2010
Journal title
Nuclear Engineering and Design Eslah
Record number
895613
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