A theoretically based critical heat flux prediction for rod bundles at PWR conditions
- 1 March 1985
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 85 (2) , 239-250
- https://doi.org/10.1016/0029-5493(85)90289-4
Abstract
No abstract availableKeywords
This publication has 3 references indexed in Scilit:
- Prediction of critical heat flux in flow boiling at low qualitiesInternational Journal of Heat and Mass Transfer, 1983
- COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and coresPublished by Office of Scientific and Technical Information (OSTI) ,1976
- Prediction of departure from nucleate boiling for an axially non-uniform heat flux distributionJournal of Nuclear Energy, 1967