FIRST STEPS TO COUPLED HYDRAULIC AND MECHANICAL CALCULATIONS WITHIN A PARAMETER STUDY TO DEFINE POSSIBLE CORE DESIGNS FOR THE CONVERSION OF FRM II

EPJ Web of Conferences

Bergeron Aurelien¹  Bojanowski Cezary¹  Shehu Kaltrina²  Reiter Christian²  Petry Winfried² 

[1] Argonne National Laboratory;Forschungs-Neutronenquelle Heinz Maier-Leibnitz (FRM II) Lichtenbergstraße 1;

关键词: research reactor;    code validation;    conversion;   

DOI  :  10.1051/epjconf/202124708011

来源: DOAJ

【 摘 要 】

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+.

【 授权许可】

Unknown