Journal article
ICONE23-2115 MODELING CRITICAL FLOW IN CRACK GEOMETRIES USING TRACE
Abstract
The TRACE thermal hydraulic system code was used to predict subcooled critical flow for three sets of experiments employing crack geometries. The first experiment measured flow through slits in thin walled sections representative of defects in steam generator tubes. The second experiment consisted of critical flow rate tests in simulated circumferential cracks in large diameter piping. The final set of data measured critical flow through cracks …
Authors
Oussoren A; Riznic J; Revankar S
Journal
The Proceedings of the International Conference on Nuclear Engineering (ICONE), Vol. 2015.23, No. 0,
Publisher
Japan Society of Mechanical Engineers
Publication Date
2015
DOI
10.1299/jsmeicone.2015.23._icone23-2_44
ISSN
2424-2934