Hot channel factors determination and evaluation for water-cooled nuclear research reactors performance

This paper presents the general outlines of the evaluation, selecting, determination, and applying peaking hot channel factors for nuclear research reactors. As an example, the uncertainty in the heat transfer coefficient is a major contributor to the reduction in nuclear research reactor performances and thermal hydraulic safety margins, where the uncertainties are due to the reactor fuel coolant channel design fabrication defects (fuel meat and clad thickness uncertainties), and the fuel element's heterogeneity. Both the uncertainties are important contributors and an area where more information may be useful in reducing this uncertainty. In this case we take the WWR-M2 nuclear reactor (Russian type) fuel coolant channel (fuel Assembly) as sample problem for applying and determination the peaking factors, and understanding this method. (author)