| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 08011 | |
| Number of page(s) | 16 | |
| Section | Research Reactors and Facilities | |
| DOI | https://doi.org/10.1051/epjconf/202124708011 | |
| Published online | 22 February 2021 | |
https://doi.org/10.1051/epjconf/202124708011
FIRST STEPS TO COUPLED HYDRAULIC AND MECHANICAL CALCULATIONS WITHIN A PARAMETER STUDY TO DEFINE POSSIBLE CORE DESIGNS FOR THE CONVERSION OF FRM II
1 Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) Lichtenbergstraße 1, Garching bei München, Germany
2 Argonne National Laboratory 9700 S Cass Ave, Lemont, IL 60439, United States
kaltrina.shehu@frm2.tum.de
cbojanowski@anl.gov
abergeron@anl.gov
infried.petry@tum.de
christian.reiter@frm2.tum.de
Published online: 22 February 2021
The Forschungs-Neutronenquelle Heinz Meier-Leibnitz (FRM II) is actively participating in the worldwide efforts on developing high-density uranium fuels in order to reduce the enrichment of fuels used in high flux research reactors. This work is part of a parameter study to define possible compatible FRM II core designs for conversion. As a first step, a code-to-code verification is performed and experimental data is used for validation. The Gambill experiment was performed in the early 1960’s in support of the HFIR program and provides results regarding the heat transfer coefficient and friction factors of water flowing through an electrically heated thin rectangular channel. A comparison is made between the Gambill Test and the results simulated by Ansys CFX and STAR-CCM+.
Key words: research reactor / code validation / conversion
© The Authors, published by EDP Sciences, 2021
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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