Calculation of tube degradation induced by dryout instability in sodium-heated steam generators
- 30 April 1977
- journal article
- Published by Elsevier in Nuclear Engineering and Design
- Vol. 41 (2) , 181-191
- https://doi.org/10.1016/0029-5493(77)90108-x
Abstract
No abstract availableKeywords
This publication has 3 references indexed in Scilit:
- A Liquid Level Detector for Reactor EnvironmentsIEEE Transactions on Nuclear Science, 1976
- Heat-transfer crisis in a steam-generating tube on heating with a liquid-metal heat carrier (coolant)Atomic Energy, 1975
- A Research Study on Internal Corrosion of High-Pressure Boilers—Final ReportJournal of Engineering for Power, 1969